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
February 22, 2010 Mr. Christopher Costanzo Vice President, Nuclear Plant Support NextEra Energy Duane Arnold, LLC 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 -BATCH 4 (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 (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 audit review from August 10, 2009 through August 14, 2009, the staff has identified areas where additional information is needed to complete the review. The staff's 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 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 February 22, 2010 Mr. Christopher Costanzo Vice President, Nuclear Plant Support NextEra Energy Duane Arnold, LLC 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 - BATCH 4 (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 (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 audit review from August 10, 2009 through August 14, 2009, the staff has identified areas where additional information is needed to complete the review. The staff's 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 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. OFFICE: PM:RPB1:DLR LA:RPOB:DLR BC:RPB1:DLR PM:RPB1:DLR NAME: BHarris IKing BPham (BBrady for) BHarris DATE: 02/22/10 02/ 19 /10 02/22/10 02/22/10 OFFICIAL AGENCY RECORD Letter to Christopher Costanzo from Brian K. Harris dated February 22, 2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION - BATCH 4 (TAC NO. MD9769)
DISTRIBUTION
- DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource ------------- B. Harris C. Eccelston K. Feintuch M. Spencer, OGC Duane Arnold Energy Center cc: Mr. M. S. Ross Vice President and Associate General Counsel Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
Ms. Marjan Mashhadi Senior Attorney Florida Power & Light Company 801 Pennsylvania Avenue, NW Suite 220 Washington, DC 20004
Mr. Steven R. Catron Manager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324
U.S. Nuclear Regulatory Commission Resident Inspector
=s Office Rural Route #1 Palo, IA 52324 Mr. Mano Nazar 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 Ms. Melanie Rasmussen Radiation Control Program Director Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319-0075
Chairman, Linn County Board of Supervisors 930 1st Street SW Cedar Rapids, IA 52404 Mr. Gene St. Pierre Vice President Fleet Organizational Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
Mr. McHenry Cornell Director, Licensing and Performance Improvement Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 ENCLOSURE DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION
RAI 4.3.3-3
=
Background===
License renewal application (LRA) Section 4.3.3, "Fatigue Of Class 1, 2 And 3 Piping And Components" and the applicant's response to request for additional information (RAI) 4.3.3-2, by letter dated October 13, 2009, states that Class 1 piping with B.31.7 methodology is dispositioned in accrordance with 10 CFR 54.21(c)(1)(ii). Furthermore, the applicant stated that as part of the evaluation, 60-year cumulative usage factors (CUFs) were evaluated based on the numbers of cycles provided in LRA Table 4.3-1.
Issue In order for the Class 1 piping with B.31.7 methodology to be appropriately dispositioned in accordance with 10 CFR 54.21(c)(1)(ii), the limits for the number of cycles that are being tracked by the Metal Fatigue of Reactor Vessel Coolant Pressure Boundary Program and the surveillance test program (STP) must be the 60-year projected cycles and not the 40-year design cycles. If the limits for the number of cycles being tracked are not the same as those used in the evaluation to disposition in accordance with 10 CFR 54.21(c)(1)(ii), then the evaluation is not valid for the period of extended operation (PEO).
Request 1. Please confirm that the limits for the number of cycles that will be tracked by the Metal Fatigue of Reactor Vessel Coolant Pressure Boundary Program and the STP are the same number of cycles that were used in the evaluation to disposition the Class 1 piping with B.31.7 methodology in accordance with 10 CFR 54.21(c)(1)(ii) and that these cycles will be incorporated into the updated final safety analysis report (UFSAR) update.
- 2. If the limits that will be tracked by the Metal Fatigue of Reactor Vessel Coolant Pressure Boundary Program and the STP are not the same cycles that were used in the evaluation to disposition the Class 1 piping with B31.7 methodology in accordance with 10 CFR 54.21(c)(1)(ii), please justify the validity of dispositioning the Class 1 piping with B.31.7 methodology in accordance with 10 CFR 54.21(c)(1)(ii) and clarify the action that is taken to ensure the CUF is below 1.0 for the Class 1 piping with B.31.7 methodology during the PEO. RAI 4.3.4-3
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Background===
In response to RAI 4.3.4-2 (part 4, 6 and 7) by letter dated October 13, 2009, a F en factor of 1.49 was used for the Alloy 600 and SB166 components. Also in its response, the applicant stated a methodology from 1995/1996 was used for calculating the F en factor of 1.49. In 2007, the staff issued Regulatory Guide 1.207, entitled "Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors," based on NUREG/CR-6909, which incorporates more recent fatgiue data for determining the F en factor for Nickel Alloys.
Issue Although Regulatory Guide 1.207 specifically applies to new reactors, the basis methodology for F en described in NUREG/CR-6909 is considered by the staff to represent the most up-to-date method for determining the F en factor for Nickel Alloys for license renewal considerations.
Request 1. Please clarify if the value of 1.49 for the F en factor is the bounding/conservative value for the Alloy 600 and SB166 components as compared to the values calculated from NUREG/CR-6909 for Nickel Alloys. If not, please justify the use of the F en factor of 1.49 for the Alloy 600 and SB166 components.
- 2. Describe the planned actions to update the CUF calculations with F en factor for Alloy 600 and SB166 components consistent with the methodology in NUREG/CR-6909 or other acceptable methods.
- 3. Describe how the assumed 72.425% overall hydrogen water chemistry (HWC) availability will be accounted for when managing these components, since this overall HWC availability has an effect on the CUF values and may fluctuate based on actual plant operations during the PEO.
RAI 4.6-1
Background
"Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants" (SRP-LR) (NUREG 1800), Section 4.6.1.1 states that containment liner plates, metal containment, penetration sleeves may be designed and/or analyzed in accordance with ASME Code requirements. The ASME Code contains explicit metal fatigue or cyclic considerations based on time-limited aging analysis (TLAAs).
Issue LRA Section 4.6, "Fatigue of Primary Containment, Piping, and Components," states that the number of safety relief value (SRV) lifts throughout the Duane Arnold Energy Center's (DAEC's) operating history have not been consistently tracked. To address LRA requirements, the historical number of SRV lifts was needed; documentation was therefore researched to determine the number of the SRV lifts from 1974 until 2007. Using this information and projecting the results for 60 years provided a projected number of 334 single SRV lifts for 60 years and a projected number of 42 multiple lifts for 60 years.
Request Provide the actual number of SRV lifts from 1974 to 2007. In addition, explain how the SRV lifts will be monitored during PEO since the number of SRV lifts were not tracked until 2007. The staff needs the above information and analyses that were performed in 2007 to confirm that the an evaluation of TLAA will remain valid for the period of extended operation as required by 10 CFR 54.21(c).(1)(ii).
RAI 4.6-2
Background
SRP-LR (NUREG 1800), Section 4.6.1.1 states that the containment liner plates (including welded joints), penetration sleeves, etc., may be designed and/or analyzed in accordance with ASME Code requirements. The ASME Code contains explicit metal fatigue or cyclic considerations based on TLAAs.
Issue LRA Section 4.6.1 states that fatigue usage factors for the suppression chamber (torus) have been projected through the PEO. These fatigue usage factors have been determined based on an assumed number of thermal cycles for 60 years of operation. The LRA does not list the actual number of thermal cycles the suppression chamber (torus) has experienced until now.
Request Explain how the numbers of thermal cycles are monitored for suppression chamber and actual count of thermal cycles the suppression chamber have experienced. The staff needs the above information that the an evaluation of the TLAA will remain valid for the PEO as required by 10 CFR 54.21(c).(1)(ii).
RAI 4.6-3
Background
SRP-LR (NUREG 1800), Section 4.6.1.1 states that containment penetration bellows may be designed and/or analyzed in accordance with ASME Code requirements. The ASME Code contains explicit metal fatigue or cyclic considerations based on TLAAs. Issue LRA Section 4.6.2 states that for vent lines bellows, thermal load is the largest contributor to displacements. The plant unique analysis report specifies 150 thermal load cycles. However, the LRA does not list the actual number of thermal cycles the bellows have experienced until now. Request Explain how the numbers of thermal cycles are monitored for containment bellows and provide the actual count of thermal cycles the bellows have experienced. The staff needs the above information and to confirm that the an evaluation of the fatigue of the bellows provided in the LRA will remain valid for the PEO as required by 10 CFR 54.21(c).(1)(ii).
RAI 4.6-4
Background
SRP-LR (NUREG 1800), Section 4.6.1.1 states that the containment liner plates (including welded joints), penetration sleeves, etc., may be designed and/or analyzed in accordance with ASME Code requirements. The ASME Code contains explicit metal fatigue or cyclic considerations based on TLAAs.
Issue LRA Section 4.6.3 states that for suppression chamber external piping and penetrations have been projected through the period of extended operation. However, LRA does not list the actual number of thermal cycles that the suppression chamber external piping and penetrations have experienced until now. In addition, the LRA states that 334 single SRV lifts are projected for 60 years, and 42 multiple lifts are projected for 60 years of operation.
Request Explain how the numbers of thermal cycles are monitored for suppression chamber external piping and penetrations, and provide the actual count of thermal cycles the suppression chamber external piping and penetrations have experienced. In addition, please provide the actual number of SRV lifts between 1974 through 2007 that were used to project the SRV lifts through the PEO. The staff needs the above information and analyses that were performed in 2007 to confirm that an evaluation of TLAA will remain valid for the PEO as required by 10 CFR 54.21(c).(1)(ii).
RAI 4.6-5
Background
SRP-LR (NUREG 1800), Section 4.6.1.1 states that metal containments may be designed and/or analyzed in accordance with ASME Code requirements. The ASME Code contains explicit metal fatigue or cyclic considerations based on TLAAs. Issue LRA Section 4.6.4 states that the stress report includes a determination that the containment vessel is exempt from fatigue analysis. This determination is based on an assumed number of load fluctuations for 40 years of operation. After increasing this number to account for the additional cycles of a 60 year life, the fatigue analysis exemption remains valid.
Request Explain why an assumed number of load fluctuations are used instead of the actual number experienced by the containment vessel. In addition, provide the basis that has been used in the stress report to determine that containment vessel is exempt for fatigue analysis. The staff needs the above information to confirm that the an evaluation of TLAA will remain valid for the PEO as required by 10 CFR 54.21(c).(1)(ii).
RAI 4.6-6
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Background===
SRP-LR (NUREG 1800), Section 4.6.1.1 states that penetration sleeves may be designed and/or analyzed in accordance with ASME Code requirements. The ASME Code contains explicit metal fatigue or cyclic considerations based on TLAAs.
Issue LRA Section 4.6.5 states that the verification of adequacy of the fluid heads penetrations was determined by comparing allowable stresses (based on assumed number of cycles) and maximum stress intensities.
Request Explain why an assumed numbers of cycles instead of actual number of cycles tracked since the start of plant operation were used to project the results for 60 years of operation. The staff needs the above information to confirm that the an evaluation of TLAA will remain valid for the PEO as required by 10 CFR 54.21(c)(1)(ii).
RAI B.3.40-1
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Background===
In the DAEC LRA Section B.3.40.7, "Parameters Monitored or Inspected," and Section B.3.40.8, "Detection of Aging Effects," the applicant stated that it will perform a volumetric examination on a minimum of 10 percent of the ASME Code Class 1 small bore butt welds in each inspection interval during the PEO. Issue The applicant's did not provide any technical basis regarding its sampling criteria.
Request Provide a justification for the sampling criteria and explain why selecting ten percent each inspection interval is adequate.
RAI B.3.40-2
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Background===
In the DAEC LRA Section B.3.40.7, "Parameters Monitored or Inspected," and Section B.3.40.8, "Detection of Aging Effects," the applicant stated that it will perform a VT-2 visual inspection during system leakage tests on its socket welds each refueling outage per the requirements of IWB-2500-1, examination Category B-P.
Issue GALL XI.M.35 recommends volumetric examinations. The applicant's program deviates from GALL recommendations. The staff believes VT-2, or any form of a surface examination, is only leakage detection. It will not detect any degradation until a component leaks and loses its intended function. Therefore, by the time an indication is detected by VT-2, the subject component has already failed.
Request Explain how visual inspection is sufficient in aging management of Class 1 socket welds. Address volumetric examination of socket welds. The staff has discussed with the applicant in length regarding this disagreement and will make it an open item until this issue is adequately addressed.
Follow-up RAI B.3.37-1
Background
In letter NG-09-0764, dated October 13, 2009, the applicant responded to RAI B.3.37-1 related to the inspection interval of the Structures Monitoring Program. The applicant explained that based on operating experience, the five and ten year +/- one year inspection interval would be adequate to detect degradation.
Issue GALL Report AMP XI.S6 states that inspection schedule for structures to be commensurate with industry codes, standards and guidelines. AMP XI.S6 further states that ACI 349.3R and ANSI/ASCE 11-90 provide an acceptable basis for addressing detection of aging effects. The staff recognizes that ACI 349-3R recommends a 10 year interval for structures subjected to a controlled interior environment. However, industry operating experience indicates that nuclear power plant structures under controlled interior environments are subjected to high radiation, high temperature, and water leakages.
Request Provide a list of in-scope structures that will be inspected on a 10 year interval, along with their ambient environment and operating experience. This information is necessary for the staff to complete its review of AMP B.3.37 and to verify that that the DAEC inspection interval for structures is commensurate with industry operating experience, and codes and standards.
RAI B.3.15-X Background The "preventive actions" program element of the GALL Report AMP XI.M21 recommends maintaining system corrosion inhibitor concentrations within the specified limits of EPRI TR-107396 to minimize corrosion and SCC. The "acceptance criteria" program element recommends that corrosion inhibitor concentrations are maintained within the limits specified in the EPRI Closed Cooling Water Chemistry Guideline, which in Table 5-1, indicates that azoles are a monitored parameter unless it can be documented that there are no copper alloys in the system. The LRA indicates in Section 3.3.1.22 that the reactor building closed cooling water system contains copper; however, the basis documents do not appear to indicate that azoles are used in the reactor building closed cooling water system. RAI B.3.15-3 requested additional information describing why azoles are not used and monitored in the reactor building closed cooling water system as suggested in the EPRI Closed Cooling Water Chemistry Guidelines. The response to this RAI stated, "The Reactor Building Closed Cooling Water (RBCCW) system soluble copper historically has been less than 100 ppb. The industry best practices recommended range is less than 200 ppb. DAEC determined that the use of azoles in the RBCCW would be unlikely to provide a measurable reduction in the system soluble copper levels." Issue The staff notes that for a filtered sample (as described in the testing procedure provided) that the solubility of copper at pH values typical of closed systems is 100 ppb or less. The test results indicating 100 ppb dissolved copper do not, therefore, indicate that the corrosion rate of copper is low as all corroded copper in excess of approximately 100 ppb would precipitate and would not be measured in the test. Request Please provide additional information indicating that the corrosion rate of copper is sufficiently low that copper corrosion inhibitors are not required.