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| | number = ML063410108 | | | number = ML063410108 |
| | issue date = 12/08/2006 | | | issue date = 12/08/2006 |
| | title = Duane Arnold Energy Center - Request for Additional Information Related to Relief Request NDE-R005 and NDE-R007 (TAC Nos. MD2521 and MD2523) | | | title = Request for Additional Information Related to Relief Request NDE-R005 and NDE-R007 (TAC Nos. MD2521 and MD2523) |
| | author name = Ennis R B | | | author name = Ennis R |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIII-1 |
| | addressee name = VanMiddlesworth G D | | | addressee name = Vanmiddlesworth G |
| | addressee affiliation = FPL Energy Duane Arnold, LLC | | | addressee affiliation = FPL Energy Duane Arnold, LLC |
| | docket = 05000331 | | | docket = 05000331 |
| | license number = DPR-049 | | | license number = DPR-049 |
| | contact person = Feintuch K D, NRR/DORL/LPL3-1, 415-3079 | | | contact person = Feintuch K, NRR/DORL/LPL3-1, 415-3079 |
| | case reference number = NDE-R007, NEDE-R005, TAC MD2521, TAC MD2523 | | | case reference number = NDE-R007, NEDE-R005, TAC MD2521, TAC MD2523 |
| | document type = Letter | | | document type = Letter |
Revision as of 09:08, 13 July 2019
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MONTHYEARML0632401082006-11-22022 November 2006 RAI Related to Relief Request NDE-R001 Project stage: RAI ML0634101082006-12-0808 December 2006 Request for Additional Information Related to Relief Request NDE-R005 and NDE-R007 (TAC Nos. MD2521 and MD2523) Project stage: RAI ML0700903572007-01-31031 January 2007 Safety Evaluation of Relief Requests for the Fourth 10-Year Interval of the Inservice Inspection Program - Duane Arnold Energy Center Project stage: Approval ML0713801832007-06-12012 June 2007 Safety Evaluation of Relief Requests NDE-R004 and NDE-R007 for the Fourth 10-Year Interval of the Inservice Inspection Program Project stage: Approval 2006-12-08
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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. 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[Table view] |
Text
December 8, 2006 Mr. Gary Van MiddlesworthSite Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - REQUEST FOR ADDITIONALINFORMATION RELATED TO RELIEF REQUEST NDE-R005 AND NDE-R007 (TAC NOS. MD2521 AND MD2523)
Dear Mr. Van Middlesworth:
By letter dated June 30, 2006, FPL Energy Duane Arnold, LLC requested approval of severalrelief requests for the fourth 10-year inservice inspection interval at the Duane Arnold Energy Center. In relief request NDE-R005, you requested relief from certain requirements for inservice inspection specified in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). In relief request NDE-R007, you requested relief from certain requirements for visual examination in Section XI of the ASME Code.The Nuclear Regulatory Commission staff is reviewing your submittal and has determined thatadditional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on December 5, 2006, Mr. Tom Byrne and members of your technical staff agreed to provide a response for NDE-R005 within one week and a response for NDE-R007 within two weeks of receipt of this RAI. If circumstances result in the need to revise your response dates, or if you have any questions, please contact Karl Feintuch at (301) 415-3079. Sincerely,/RA/Richard B. Ennis, Senior Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-331
Enclosure:
RAI cc w/encl: See next page
ML063410108OFFICELPL3-1/PMLPL3-1/PMLPL3-1/LAAPLB/BCCFEB/BCLPL3-1/BC NAMEKFeintuchREnnisTHarrisLMrowcaKGrussLRaghavan DATE12/7/0612/7/0612/7/0612/7/0612/8/0612/8/06 Duane Arnold Energy Center cc:
Mr. J. A. StallSenior Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. M. S. RossManaging Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. R. E. HelfrichSenior Attorney Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. W. E. WebsterVice President, Nuclear Operations Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420John BjorsethSite Director Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324Steven R. CatronManager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324U. S. Nuclear Regulatory CommissionResident Inspector's Office Rural Route #1 Palo, IA 52324Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351Mr. M. WarnerVice President, Nuclear Operations Support Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Mr. D. A. CurtlandPlant Manager Duane Arnold Energy Center 3277 DAEC Rd.
Palo, IA 52324-9785Mr. R. S. KundalkarVice President, Nuclear Engineering Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420Daniel K. McGheeIowa Department of Public Health Bureau of Radiological Health 321 East 12th Street Lucas State Office Building, 5th Floor Des Moines, IA 50319-0075Chairman, Linn CountyBoard of Supervisors 930 1st Street SW Cedar Rapids, IA 52404October 12, 2006 EnclosureREQUEST FOR ADDITIONAL INFORMATIONRELATED TORELIEF REQUESTS NDE-R005 AND NDE-R007DUANE ARNOLD ENERGY CENTERDOCKET NO. 50-331By letter dated June 30, 2006, FPL Energy Duane Arnold, LLC (FPL Energy or the licensee)requested approval of several relief requests for the fourth 10-year inservice inspection (ISI) interval at the Duane Arnold Energy Center (DAEC). The Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that the following information will be needed for the staff to complete its review. Relief Request NDE-R005 1.Page 29 of 45 of the DAEC Fourth Ten Year ISI Plan - Relief Request NDE-R005 statesthat "This Table shows the final consequence ranking has not changed for individual linesegments, and therefore the change in risk assessment for the new inspection interval as compared to the original RI-ISI [risk-informed ISI] submittal meets the acceptance criteria of the original RI-ISI submittal." However we identified some inconsistenciesbelow:1a. Note (16) of this table says that "The risk rank was increased from low to medium as an effect from t he Updated PSA [probabilistic safety assessment]."
1b.The number of welds selected for the nondestructive examination for the fourth intervalare reduced, especially for control rod drive system. Please provide an explanation for this inconsistency and the rationale for the reduction.1c.In Table 1, the risk ranking of the reactor core isolation cooling system is increased fromlow to medium as an effect from the updated PSA, but none of the welds were selected for the inspection, please explain. 2.Where your explanations in response to items 1a, 1b, and 1c warrant, please provideresults from the cumulative risk impacts analysis demonstrating that the change in risk associated with implementation of the probabilistic risk assessment (PRA) Revision 5B model is consistent with the change in the Electric Power Research Institute TR-112657 Revision B-A risk guidelines.3.The RI-ISI consequence results should also be ranked based on the impact oncontainment performance. Please provide the DAEC large early release frequency (LERF) and PRA model version/date used in support of the RI-ISI relief. 4.There is no specific mention of the Boiling Water Reactors Owners' Group PRAcertification associated with the LERF calculation. Please confirm if this certification has or has not been performed. If the certification has been performed, have the Level A and B Facts and Observations (F&Os) that the peer review team identified regarding LERF been resolved and/or incorporated into the models? If the F&Os have not been incorporated, please state why the unincorporated F&Os are not expected to have an impact on the RI-ISI consequence evaluation.Relief Request NDE-R0071.The system pressure test for nonisolable buried components in the Essential SeviceWater (ESW) piping requires a test to confirm that flow during operation is not impaired.
Relief Request NDE-R007 proposes an alternative to use the results of quarterly pump testing under the inservice test (IST) program for pumps, along with a visual examination of the ground surface, to verify that the flow is not impaired in the buried portion of ESW piping. The NRC staff requests the licensee to clarify how the results of the pump test will be used to confirm adequate flow from a qualitative determination of flow impairment in the buried ESW piping.