Letter Sequence RAI |
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MONTHYEARML0901403732009-02-10010 February 2009 Federal Register Notice of Acceptance for Docketing of the Application an Notice of Opportunity for Hearing Regarding Renewal of License Duane Arnold Energy Center for Additional 20-Year Period Project stage: Request ML0901403992009-02-10010 February 2009 Determination of Acceptability and Sufficiency for Docketing and Opportunity for a Hearing Regarding the Application from FPL Energy Duane Arnold LLC, for Renewal of the Operating License for the Duane Arnold Energy Center Project stage: Other ML0912001872009-05-28028 May 2009 Schedule to Conduct the Review of the Duane Arnold License Renewal Application Project stage: Approval ML0919400922009-07-20020 July 2009 Audit Plan for Aging Management Program Site Audit Regarding Duane Arnold Energy Center License Renewal Application Project stage: Other ML0919801782009-08-0707 August 2009 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Section 2.5 Project stage: RAI ML0920804142009-08-0707 August 2009 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Section 2.2 and 2.3 Project stage: RAI ML0921205392009-08-0707 August 2009 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Section 2.3 Project stage: RAI ML0921502092009-08-0707 August 2009 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application-Section 2.3.3.1.1 Tac MD9769) Project stage: RAI ML0919701722009-08-14014 August 2009 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - TLAA 4.2, B.3.12, B.3.13, B.3.14, B.3.35 Project stage: RAI ML0921703562009-08-18018 August 2009 Project Manager Change for the License Renewal Project (Safety) for Duane Arnold Nuclear Power Station Project stage: Other NG-09-0645, Response to Request for Additional Information Regarding Section 2.5 of the License Renewal Application2009-09-0303 September 2009 Response to Request for Additional Information Regarding Section 2.5 of the License Renewal Application Project stage: Response to RAI NG-09-0644, Response to Request for Additional Information Regarding Section 2.3 of the License Renewal Application2009-09-0303 September 2009 Response to Request for Additional Information Regarding Section 2.3 of the License Renewal Application Project stage: Response to RAI NG-09-0643, Response to Request for Additional Information Regarding Sections 2.2 and 2.3 of the Duane Arnold Energy Center License Renewal Application2009-09-0303 September 2009 Response to Request for Additional Information Regarding Sections 2.2 and 2.3 of the Duane Arnold Energy Center License Renewal Application Project stage: Response to RAI NG-09-0646, Response to Request for Additional Information Regarding Section 2.3.3.11 of the Duane Arnold Energy Center License Renewal Application2009-09-0303 September 2009 Response to Request for Additional Information Regarding Section 2.3.3.11 of the Duane Arnold Energy Center License Renewal Application Project stage: Response to RAI ML0923103582009-09-14014 September 2009 RAI for the Review of the Duane Arnold Energy Center License Renewal Application Project stage: RAI ML0925703842009-09-17017 September 2009 RAI for the Review of the Duane Arnold Energy Center License Renewal Application - Section 2.4 Project stage: RAI ML0925804092009-09-24024 September 2009 Request for Additional Information Regarding Use of Boral Neutron Absorbing Material in Spent Fuel Pool Racks and the Protective Coating Monitoring and Maintenance Program Project stage: RAI ML0925805472009-09-24024 September 2009 Request for Additional Information, License Renewal Application - Time-Limited Aging Analysis Section 4.2, Aging Management Programs Project stage: RAI ML0928705372009-10-16016 October 2009 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Batch 2 Project stage: RAI ML0928704532009-11-0202 November 2009 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Scoping and Screening Review Project stage: RAI ML0929404352009-11-0202 November 2009 Scoping and Screening Audit Report Regarding the Review of the Duane Arnold Energy Center License Renewal Application Project stage: Approval ML0929405912009-11-13013 November 2009 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Engineering Review Branch 1 Aging Management Review Line Items Project stage: RAI ML0930105392009-11-30030 November 2009 Audit Report Regarding the Duane Arnold Energy Center License Renewal Application Project stage: Other ML0934516502009-12-29029 December 2009 Revision of Schedule for the Conduct of Review of the Duane Arnold Energy Center License Renewal Application Project stage: Approval ML0936300342010-01-0606 January 2010 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Batch 3 Project stage: RAI ML1004710372010-02-22022 February 2010 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application-Batch 4 (TAC No, MD9769) Project stage: RAI ML1010502352010-05-0303 May 2010 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Buried Piping Project stage: RAI NG-10-0309, Supplemental Information and Response to Request for Additional Information Related to License Renewal Application2010-05-28028 May 2010 Supplemental Information and Response to Request for Additional Information Related to License Renewal Application Project stage: Response to RAI NG-10-0383, Supplemental Information Related to the License Renewal Application - Buried Piping2010-07-29029 July 2010 Supplemental Information Related to the License Renewal Application - Buried Piping Project stage: Supplement ML1022801092010-08-16016 August 2010 Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Low Voltage Cables Project stage: RAI 2009-08-07
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Category:Letter
MONTHYEARML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities NG-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 ML24072A0292024-03-29029 March 2024 Nextera Energy Duane Arnold, Llc. Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) NG-24-0002, 2023 Annual Exposure Report - Form 5s2024-03-0606 March 2024 2023 Annual Exposure Report - Form 5s 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 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) 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 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment 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 ML23137A1672023-05-11011 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report 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 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) ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22339A0012022-12-22022 December 2022 Acceptance of Requested Licensing Action Amendment Request for Common Emergency Plan IR 05000331/20220032022-12-13013 December 2022 NRC Inspection Report No. 05000331/2022003 (Drss) ML22285A0072022-10-13013 October 2022 NRC Analysis of NextEra Energy Duane Arnold'S Decommissioning Funding Status Report, Docket No. 50-331 IR 05000331/20220022022-07-13013 July 2022 NRC Inspection Report Nos. 05000331/2022002(DNMS) and 07200032/2022002(DNMS) ML22090A1922022-05-26026 May 2022 Letter to B. Coffey, FPL from M. Doell - Duane Arnold Post Shutdown Activities Report Review Letter ML22132A2872022-05-24024 May 2022 ISFSI DQAP Approval Letter ML22111A0332022-05-20020 May 2022 Operating License Page Correction Letter to B. Coffey, Florida Power and Light, from M. Doell 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 ML22089A0492022-05-12012 May 2022 Sfmp Review Letter 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. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022 Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative IR 05000331/20224012022-04-27027 April 2022 Decommissioning Security Inspection Report 05000331/2022401 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval L-2022-068, NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 22022-04-25025 April 2022 NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 2 NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. 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-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22080A1822022-03-22022 March 2022 Letter to B. Coffey from M. Doell - Duane Arnold ISFSI QAPD RAI Letter L-2022-012, Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)2022-03-16016 March 2022 Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22059A7462022-03-10010 March 2022 ISFSI-Only Physical Security Plan License Amendment Approval NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks IR 05000331/20220012022-03-0404 March 2022 Subject: NRC Inspection Report Nos. 05000331/2022001(DNMS) and 07200032/2022001(DNMS) NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22007A2722022-02-11011 February 2022 Cover Letter - NRC Duane Arnold Exemption Issuance 2024-08-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML22005A0862022-01-0404 January 2022 1-4-2022 Email Communication to Duane Arnold Regarding Its ISFSI Related Exemption Request on Supplemental Information Needed ML21335A0712021-12-0101 December 2021 Request for Additional Information - Duane Arnold Energy Center ISFSI Only Emergency Plan ML21335A0702021-12-0101 December 2021 Cover Letter to B. Coffey from K. Conway - Duane Arnold Energy Center RAI Re License Amendment Request for ISFSI Only Emergency Plan ML21250A3002021-09-0808 September 2021 Defueled Physical Security Plan RAI Cover Letter ML21006A4052021-01-0606 January 2021 NRR E-mail Capture - Final RAI - Duane Arnold - Post-Shutdown Decommissioning Activities Report ML20316A0212020-11-10010 November 2020 NRR E-mail Capture - Final RAI - Duane Arnold - Duane Arnold Amendment for Proposed Defueled EP and EAL Scheme ML20153A3772020-05-28028 May 2020 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center Quality Assurance Topical Report (FPL-3) - EPID L-2020-LLQ-0002) ML20141L8132020-05-19019 May 2020 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center (DAEC) - Exemption Request for Security Training Requirements Due to COVID-19 Pandemic - EPID L-2020-LLE-0042 to 45, L-2020-LLE-0051 ML20133K0482020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20127H8662020-05-0505 May 2020 NRR E-mail Capture - Duane Arnold Energy Center (DAEC) - Request for Additional Information (RAI) - Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 1O CFR 50.75(h)(1)(iv) - EPID L-2020-LLE-0011 ML19280A0352019-10-0404 October 2019 NRR E-mail Capture - Final - RAI Related to License Amendment Request (TSCR-182) for Proposed Changes to the Emergency Plan for Permanently Defueled Conditions at Duane Arnold Energy Center (DAEC) - L-2019-LLA-0075 ML18283B0522018-10-0909 October 2018 NRR E-mail Capture - Final Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420 ML18255A2922018-09-11011 September 2018 NRR E-mail Capture - Draft Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420 ML18247A2002018-08-21021 August 2018 E-Mailed Request for Information for Duane Arnold, Dated 08/21/18 (DRS-M.Holmberg) ML18166A2982018-06-15015 June 2018 NRR E-mail Capture - Draft Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420 ML18088A0102018-03-28028 March 2018 NRR E-mail Capture - Final RAI for Duane Arnold (DAEC) 5th-10 Year ISI (RR-05) ML18058A0522018-02-27027 February 2018 Enclosurequest for Additional Information (Letter: RAI Regarding Florida Power and Light/Nextera Decommissioning Funding Plan Updates for St. Lucie, Units 1 & 2; Seabrook Station; Duane Arnold Energy Center; and Point Beach, Units 1 and 2) ML18037B0032018-02-0606 February 2018 NRR E-mail Capture - Draft Request for Additional Information - Duane Arnold Energy Center (DAEC) - License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating - EPID L-2017-LLA-0288 ML17347A8752017-12-12012 December 2017 NRR E-mail Capture - Second Round of Request for Additional Information - Duane Arnold Energy Center (DAEC) - LAR to Adopt TST-542, Revision 2, Reactor Pressure Vessel Water Inventory Control - CAC No. MF9829 ML17277A3652017-10-0404 October 2017 NRR E-mail Capture - Final Request for Additional Information - Duane Arnold - Application to Revise Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control - CAC No. MF9829 ML17240A0082017-08-25025 August 2017 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center (DAEC) - Fifth Ten Year Service Inspection Interval - Relief Request No. RR-04, Rev. 0 - Proposed Alternative for Seal Weld Procedure Qualification - MF937 ML17220A3332017-08-0808 August 2017 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center - Relief Request No. RR-03 - Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds - CAC No. MF9374 ML17159A7962017-06-0707 June 2017 17 Duane Arnold Energy Center - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML17068A0632017-03-0808 March 2017 NRR E-mail Capture - Final - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - Revision to Staff Augmentation Times in the Duane Arnold Energy Center (DAEC) Emergency Plan (Eplan) - MF8390 ML16333A4622016-11-28028 November 2016 NRR E-mail Capture - Final Request for Additional Information - Duane Arnold Energy Center - LAR - SFP Criticality - MF7486 ML16326A0092016-11-18018 November 2016 NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209 ML16313A0742016-11-0808 November 2016 NextEra Audit Plan Nov 2016 (DAEC SFP Criticality LAR) ML16075A0032016-03-14014 March 2016 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center - LAR to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specifications 2.1.1, Reactor Core Safety Limits - MF6618 ML16074A3142016-03-14014 March 2016 NRR E-mail Capture - Second Round RAIs - Duane Arnold Energy Center - LAR (TSCR-143) to Extend Containment Leakage Test Frequency - MF6619 ML16021A0122016-01-21021 January 2016 Request for Additional Information by the Containment & Ventilation Branch and PRA Licensing Branch License Amendment Request - Extension of the 10 CFR 50 Appendix J Containment Type a & Type C Test Intervals ML16022A0092016-01-21021 January 2016 NRR E-mail Capture - Request for Additional Information - LAR to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report - MF6617 ML16014A6962016-01-0707 January 2016 E-Mail: Duane Arnold, MOD/50.59 Inspection Request for Information (Jsp) ML16005A6082015-12-24024 December 2015 E-Mail: Duane Arnold Request for Information; December 24, 2015 (AAS) ML15175A0652015-06-23023 June 2015 Ltr. 06/23/15 Duane Arnold Energy Center - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information Inspection Report 05000331/2015003 (Axd) ML14057A7562014-02-25025 February 2014 14 Duane Arnold CDBI Request for Information ML14031A1462014-01-29029 January 2014 Update to NextEra Energy Duane Arnold, Llc'S Response to NRC Request for Additional Information Associated with Near-Term Task Force Recommendations ML13323B4432013-11-26026 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13255A1982013-09-16016 September 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13175A3932013-06-27027 June 2013 Request for Additional Information for Review Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML13154A5112013-06-0404 June 2013 Rai'S Following Ifib Analysis of NextEra Energy'S 2013 Decommissioning Funding Status Reports for Duane Arnold Energy Center and Point Beach Units 1 and 2 ML12107A0592012-04-11011 April 2012 NRR E-mail Capture - ME7246 - DAEC - Request for Additional Information (RAI) Relief Requests NDR-R003, R010, R011, R014, R015 ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML1201203182012-01-17017 January 2012 Request for Additional Information Amendment to Change Emergency Action Levels ML12011A0602012-01-0404 January 2012 NRR E-mail Capture - ME6508 - DAEC - Emergency Action Level (EAL) Changes ML1132105812011-11-28028 November 2011 Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies. 2024-07-12
[Table view] |
Text
September 24, 2009 Mr. Christopher Costanzo Vice President, Nuclear Plant Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION -
TIME-LIMITED AGING ANALYSIS SECTION 4.2, AGING MANAGEMENT PROGRAMS B.3.12, B.3.13, B.3.14 AND B.3.35 (TAC NO. MD9769)
Dear Mr. Costanzo:
By letter dated September 30, 2008, as supplemented by letter dated January 23, 2009, FPL Energy Duane Arnold, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) for renewal of Operating License No. DPR-49 for the Duane Arnold Energy Center. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants.
During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the enclosure. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Mr. Ken Putnam, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2277 or by e-mail at Brian.Harris2@nrc.gov.
Sincerely,
/RA/
Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
As stated cc w/encl: See next page
September 24, 2009 Mr. Christopher Costanzo Vice President, Nuclear Plant Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION -
TIME-LIMITED AGING ANALYSIS SECTION 4.2, AGING MANAGEMENT PROGRAMS B.3.12, B.3.13, B.3.14 AND B.3.35 (TAC NO. MD9769)
Dear Mr. Costanzo:
By letter dated September 30, 2008, as supplemented by letter dated January 23, 2009, FPL Energy Duane Arnold, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54) for renewal of Operating License No. DPR-49 for the Duane Arnold Energy Center. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants.
During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the enclosure. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Mr. Ken Putnam, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2277 or by e-mail at Brian.Harris2@nrc.gov.
Sincerely,
/RA/
Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
See next page ADAMS Accession No.: ML092580547 OFFICE: PM:RPB1:DLR LA:DLR BC:RPB1:DLR PM:RPB1:DLR NAME: BHarris SFigueroa DPelton BHarris (Signature)
DATE: 09/22/09 09/22/09 09/22/09 09/24/09 OFFICIAL AGENCY RECORD
Letter to Christopher Costanzo from Brian K. Harris dated September 24, 2009
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION -
TIME-LIMITED AGING ANALYSIS SECTION 4.2, AGING MANAGEMENT PROGRAMS B.3.12, B.3.13, B.3.14 AND B.3.35 (TAC NO. MD9769)
DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
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B. Harris C. Eccelston M. Spencer K. Feintuch
Duane Arnold Energy Center cc:
Mr. M. S. Ross Ms. Melanie Rasmussen Vice President and Associate Radiation Control Program Director General Counsel Bureau of Radiological Health Florida Power & Light Company Iowa Department of Public Health P.O. Box 14000 Lucas State Office Building, 5th Floor Juno Beach, FL 33408-0420 321 East 12th Street Des Moines, IA 50319-0075 Ms. Marjan Mashhadi Senior Attorney Chairman, Linn County Florida Power & Light Company Board of Supervisors 801 Pennsylvania Avenue, NW 930 1st Street SW Suite 220 Cedar Rapids, IA 52404 Washington, DC 20004 Mr. Raj Kundalkar, Vice President Mr. Steven R. Catron Fleet Organizational Support Manager, Regulatory Affairs Florida Power & Light Company Duane Arnold Energy Center P.O. Box 14000 3277 DAEC Road Juno Beach, FL 33408-0420 Palo, IA 52324 Mr. McHenry Cornell U.S. Nuclear Regulatory Commission Director, Licensing and Performance Resident Inspector=s Office Improvement Rural Route #1 Florida Power & Light Company Palo, IA 52324 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Mano Nazir Senior Vice President and Nuclear Chief Operating Officer Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408 Mr. D. A. Curtland Plant Manager Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785 Abdy Khanpour Vice President, Engineering Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408
REQUEST FOR ADDITIONAL INFORMATION RELATED TO TIME LIMITED AGING ANALYSES SECTION 4.2 AND AGING MANAGEMENT PROGRAMS B.3.12, B.3.13, B.3.14, AND B.3.35 LICENSE RENEWAL APPLICATION FOR DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 RAI 4.2.6-1 According to the applicant the reflood thermal shock analysis that is applicable to Duane Arnold Energy Center (DAEC) reactor vessel (RV) indicates that the peak stress intensity factor for DAEC RV is bounded by the fracture toughness value of the vessel material under the reflood thermal shock conditions. The staff requests that the applicant provide information regarding the following items:
(1) The methodology that was used to obtain the peak stress intensity factor of the RV material under the reflood thermal shock conditions, (2) and effect of maximum vessel irradiation (E > 1 MeV) at 54 effective full power years (EFPY) at the mid-core inside RV location on the applicants analysis.
RAI 4.2.6-2 The DAEC stainless steel core shroud is subject to radiation embrittlement resulting in loss of structural integrity due to a low pressure coolant injection thermal shock transient. Therefore, the staff requests that the applicant include a reflood thermal shock analysis as a part of a time-limited aging analysis (TLAA) for the core shroud at DAEC.
RAI 4.2.3-1 The current RV pressure-temperature (P-T) limits are valid through 32 EFPY. The applicant does not address as to how it will manage any change in P-T limits as a result of a change in neutron fluence values during the extended period of operation. Therefore, the staff requests that the applicant state the following items in Section 4.2.3 of the (LRA):
(1) Changes in the P-T limits during the extended period of operation will be managed by using approved fluence calculations which address the units operating conditions (i.e., thermal power level, core design, etc.) in conjunction with surveillance capsule results.
(2) Any change in P-T limits will be implemented by the license amendment process (i.e., modifications of technical specifications) and will meet the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.60 and 10 CFR Part 50, Appendix G.
ENCLOSURE
RAI 4.2.4-1 The applicant identified one circumferential weld, DE (VCB-A2), in the beltline region.
Probability of failure (PoF) results were calculated for 60 years (54 EFPY) for the RV beltline circumferential weld, including the consideration of the low temperature overpressurization (LTOP) occurrence probability of 1x10-3 per year. The PoF for the beltline circumferential weld due to an LTOP event was calculated to be 1.5x10-9 per reactor-year at 54 EFPY and 2.5x10-11 per year for 90% inspection. Please provide the calculation/analyses used to derive the 54 EFPY PoF values for the beltline circumferential weld. Include the limiting circumferential weld surface fluence value, and the corresponding calculated mean nil-ductility reference temperature (RTNDT).
RAI 4.2.4-2 The applicant stated that it will utilize the same procedures and training used to limit RV cold over-pressure events as those approved by the NRC when the DAEC requested approval of the BWRVIP-05, BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations, technical alternative for the term of the current operating license. Include specific reference to the stated NRC approved request.
RAI 4.2.5-1 In the BWRVIP-05 safety evaluation (SE), the staff concluded that the applicant need not examine the reactor pressure vessel (RPV) circumferential shell welds, if the corresponding volumetric examinations of the RV axial shell welds do not reveal the presence of an age-related degradation mechanism. Confirm whether previous volumetric examinations of the RV axial shell welds have shown any indication of cracking or other age-related degradation mechanisms in the welds.
RAI 4.2.5-2 PoF results were calculated for 60 years (54 EFPY) for the RV beltline axial welds, including the consideration of the LTOP occurrence probability of 1x10-3 per year. The PoF for the limiting beltline axial weld due to an LTOP event was calculated to be 2.24 x10-7 at 54 EFPY and 3.74x10-9 per year for 90% inspection. Please provide the calculation/analyses used to derive the 54 EFPY PoF values for the limiting beltline axial weld. Include the limiting axial weld surface fluence value, and the corresponding calculated mean RTNDT.
RAI 4.2.7-1 The applicant stated that the loss of preload over time in core plate hold-down bolts due to stress relaxation is considered as a TLAA. Therefore, the staff requests that the applicant provide a TLAA analysis (if available) for the core plate-hold down bolts for staff review and approval. If this analysis is not currently available, the applicant shall make a commitment to submit this analysis two years prior to entering the period of extended operation. The staff expects that this analysis shall use projected neutron fluence values to the end of the extended period of operation.
Since core plate wedges are not installed at DAEC, consistent with the inspection guidance specified in item 10 of Table 3-2 of the BWRVIP-25 report, BWR Core Plate Inspection and Flaw Evaluation Guidelines, the applicant shall continue enhanced visual inspection (EVT-1) of the core plate hold-down bolts. Therefore, the staff requests that the applicant confirm that it will continue performing EVT-1 inspections of the core plate hold-down bolts and use ultrasonic testing (UT) from a location above the core plate when such a UT technique is developed by the industry.
RAI 4.2.7-2 Table IV.B1-17 of the Generic Aging Lessons Learned (GALL-NUREG-1801) requires that 5%
of the top guide locations that are exposed to a neutron fluence exceeding the irradiation-assisted stress corrosion cracking (IASCC) threshold limit of 5 x 1020 (E > 1 MeV) prior to the period of extended operation, be inspected using an EVT-1 technique within six years after the period of extended operation. An additional 5% of the top guide locations with an exposure to a neutron fluence value greater than IASCC threshold limit shall be inspected within twelve years after entering into the period of extended operation. The staff requests that the applicant include a statement in Section 4.2.7 that refers to Commitments 2 and 3.
RAI 4.2.7-3 The applicant stated that core shroud circumferential welds H3, H4, H5 and vertical welds V3 though V8 have exceeded the IASCC threshold neutron fluence value. Hence, the staff requests that the applicant confirm that it will implement the requirements specified in footnote 4 of Tables 2-1 and C-9 of the BWRVIP-76, BWR Vessel Internals Project BWR Core Shroud Inspection and Flaw Evaluation Guidelines, report for these core shroud welds.
RAI B.3.12-1 Consistent with the requirement specified in Generic Letter 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, DAEC included a portion of small bore piping (less than
- 4) in its American Society of Mechanical Engineers (ASME) Code,Section XI Inservice Inspection (ISI) program. In this context, the staff requests that the applicant provide the following information:
(1) Previous plant experience regarding the aging degradation of small bore piping welds, (2) type of prior inspections that were performed thus far on the small bore piping welds, (3) and inspection results followed by any corrective actions that were taken so far to prevent recurrence of any aging degradation in small bore piping welds.
RAI B.3.12-2 DAEC stated that it identified intergranular stress corrosion cracking (IGSCC) in three recirculation riser nozzle-to-safe end welds (RRB-F002, RRD-F002 and RRF-002) and weld overlays were incorporated on these welds as a mitigation technique to prevent further aging degradation. The staff requests that the applicant provide the following information with respect to these welds:
(1) Type of the weld materials that were originally used to fabricate these welds, (2) mitigation technique (e.g., stress improvement) that was implemented, if any, on these welds prior to the identification of IGSCC, (3) confirm whether these cracks were through wall prior to the application of the weld overlays, (4) and future inspection plans for these welds.
RAI B.3.13-1 The applicant stated that the frequency and the method of inspection specified in BWRVIP A, Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines, will be implemented for the attachment welds. If furnace-sensitized stainless steel components exist in these systems at DAEC, please provide details on how the aging management program is implemented, i.e. any additional augmented inspection program for the furnace-sensitized stainless steel materials. These requirements apply to, but are not limited to, jet pump raiser brace attachments, core spray piping bracket attachments, steam dryer support and hold down brackets, feedwater spargers, guide rods, and surveillance sample holders.
RAI B.3.14-1 The applicant should confirm whether it is incorporating hydrogen water chemistry (HWC) and/or noble metal chemical addition (NMCA) in its water chemistry program. The applicant should provide the following information with respect to the implementation of HWC and/or NMCA in its water chemistry program.
Confirm the method of controlling HWC and/or NMCA in the RV. The applicant should explain how this implementation has affected the plant chemical parameters. Provide details on the methods for determining the effectiveness of HWC and/or NMCA by using the following parameters:
(1) Electrochemical potential (ECP)
(2) Feedwater hydrogen flow (3) Main steam line oxygen content (4) Hydrogen/oxygen molar ratio If ECP is measured to verify the effectiveness of HWC and/or NMCA, provide information regarding the locations at which the ECP measurements are taken.
RAI B.3.14-2 BWRVIP-18-A, BWR Core Spray Inspection and Flaw Guidelines.
Some welds that are not accessible in core spray systems require inspections per Table 3-5 of the BWRVIP-18-A report. In this context, the staff requests that the applicant provide the following information:
(1) Type of prior inspections that were performed thus far on these welds, (2) and inspection results followed by any corrective actions that were taken so far to prevent recurrence of any aging degradation of these welds.
RAI B.3.14-3 BWRVIP-25, BWR Core Plate Inspection and Flaw Evaluation Guidelines.
(1) Identify the type of core plugs, if any, that are currently present in the core plate assembly (i.e., spring loaded plug or fillet all around plug) at DAEC, (2) and identify the type of inspections that were performed thus far on these plugs, the results of the inspections and corrective actions taken to prevent recurrence of any aging degradation.
RAI B.3.14-4 To ensure that the aging degradation in the following reactor vessel internals (RVI) components is adequately monitored, the staff requests that the applicant identify which of the following RVI components exhibited cracking, the corrective actions taken and any additional augmented inspections implemented as part of corrective actions:
(A) core spray system; (B) core plate; (C) steam dryer; (D) top guide; (E) control rod drive guide tube, stub tube, in-core housing and dry tube; (F) and RV penetrations RAI B.3.14-5 BWRVIP-76, BWR Core Shroud Inspection and Flaw Evaluation Guidelines.
(A) With regard to previous inspections of the core shroud components, the staff requests that the applicant provide the following information:
(1) Identify which core shroud welds showed indications during previous inspections,
(2) and discuss tie rod repairs, if any, that were performed at DAEC.
(B) Reduction in ductility and fracture toughness can occur in stainless steel RVI components when they are exposed to high energy neutrons (E > 1 MeV). In August 2006, the Boling Water Reactor Vessel and Internals Project (BWRVIP) issued the staff-approved BWRVIP-100-A report, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds, which discusses fracture toughness results for the irradiated stainless steel materials. For stainless steel materials with exposure to a neutron fluence value equal to or greater than 1 X 1021 n/cm2 (E > 1 MeV), the BWRVIP-100-A report identified a lower fracture toughness value than that reported in Appendix C of the BWRVIP-76 report.
During the license renewal period, core shroud welds and base materials may be exposed to neutron fluence values 1 X 1021 n/cm2 (E > 1 MeV) or greater. Since the inspection frequency in the BWRVIP-76 report is based on fracture toughness values which are less conservative than the BWRVIP-100-A report, the staff requests that the applicant make a commitment that it will incorporate the crack growth rate evaluations specified in the BWRVIP-100-A report and develop generic inspection intervals for core shroud welds that are exposed to a neutron fluence value equal to or greater than 1 X 1021 n/cm2 (E > 1 MeV).
(C) The applicant shall make the following statement in aging management program (AMP) B.3.14, When a tie rod repair is considered as a repair option, the implications of the Hatch, Unit 1 tie rod repair cracking and the revised inspection guidelines, if any, developed by the BWRVIP will be used.
(D) The staffs guidance in Table IV.B1 of the GALL Report lists two potentially applicable aging effects for BWR core shrouds and core shroud repair assembly components that are made from either stainless steel (including cast austenitic stainless steel) or nickel alloys: (1) loss of material due to pitting and crevice corrosion (refer to GALL Aging Management Review [AMR] IV.B1-15), and (2) cumulative fatigue damage (refer to GALL AMR Item IV.B1-14). The BWRVIP-76 report does not address these aging effects, hence the staff requests that the applicant revise the LRA to include the aforementioned aging effects and perform necessary TLAA, if any, for the core shroud components.
RAI B.3.14-6 BWRVIP-41, BWR Vessel and Internals Project, Jet Pump Assembly, Inspection and Flaw Evaluation.
(A) The staff requests that the applicant provide information regarding DAECs plant-specific experience related to the cracking of the jet pump components, including any corrective actions or subsequent re-inspections if cracking has been observed.
(B) According to Table 3.3-1 of the BWRVIP-41 report, jet pump thermal sleeve welds have limited access for visual inspections and, therefore, the staff requests that the applicant provide the following information with respect to these welds. The staff
determined that the applicants response to the following items is essential in order to assess the applicants capability in managing aging degradation in these welds:
(1) previous inspections and the results of the inspections that were performed on these welds, (2) and if no inspections have been performed so far, the applicants future plans to inspect these welds. A technical explanation is required if the applicant proposes to not inspect these welds during the license renewal period.
RAI B.3.14-7 Access Hole Covers The AMP does not address augmented inspection of access hole covers which is required in accordance with the requirements of GALL AMR Item IV-B.1.1-d.
RAI B.3.14-8 Reactor Vessel Flange Leak Detection Line Crack initiation and growth due to thermal and mechanical loading or stress corrosion cracking (SCC) could occur in the BWR reactor vessel flange leak detection line. In accordance with the requirements of Table IV item A1.1.5 in the GALL report, a plant-specific AMP is to be evaluated for this component. In Appendix C of the LRA, the applicant stated that the AMP for this item will include implementation of BWR water chemistry and one time inspection. The staff determined that the one-time inspection is not adequate to identify cracking due to SCC in a timely manner. Hence, the staff requests that the applicant provide justification for using a one-time inspection as a part of the AMP for managing this aging effect in the reactor vessel flange leak detection line.
RAI B.3.35-1 The staff requests that the applicant include the following statements in the Updated Final Safety Analysis Report and commitment table of the LRA:
(1) The applicant will obtain NRC approval of any change in the withdrawal schedules of the RV surveillance capsules, (2) and if a standby capsule is removed from the RV without the intent to test it, the capsule will be stored in manner which maintains it in a condition which would permit its future use, including during the period of extended operation, if necessary.