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TAC:MD6814, Improved BPWS Control Rod Insertion Process (NEDO-33091) (Open) |
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Category:Letter
MONTHYEARIR 05000331/20240022024-10-25025 October 2024 NRC Inspection Report No. 07200032/2024001 and 05000331/2024002 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24163A0012024-08-0505 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-24-0001, 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update2024-03-0606 March 2024 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update NG-24-0002, 2023 Annual Exposure Report - Form 5s2024-03-0606 March 2024 2023 Annual Exposure Report - Form 5s 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 Arnolds 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-22-0050, 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 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report 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-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s 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 2024-09-04
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML22111A0332022-05-20020 May 2022 Operating License Page Correction Letter to B. Coffey, Florida Power and Light, from M. Doell ML22028A2822022-02-0303 February 2022 Defueled Physical Security Plan License Amendment Approval ML21067A6422021-05-13013 May 2021 Cyber Security License Amendment Approval ML20219A0882020-08-0707 August 2020 Correction Letter for Amendment No. 312 Removal of License Condition 2.C.(3), Fire Protection Program ML20184A0032020-07-30030 July 2020 Issuance of Amendment No. 312 Removal of License Condition 2.C.(3), Fire Protection Program ML20134J1042020-07-10010 July 2020 Issuance of Amendment No. 311 to Revise Operating License and Technical Specifications for Permanently Defueled Conditions ML20083G0082020-04-29029 April 2020 Issuance of Amendment No. 310 Changes to the Post-Shutdown Emergency Plan for Duane Arnold Energy Center ML19310C2042020-01-0202 January 2020 Issuance of Amendment No. 309 to Align Technical Specifications Staffing and Administrative Requirements ML18292A5662018-11-30030 November 2018 Issuance of Amendment 308 to Upgrade Emergency Action Level Scheme for Duane Arnold Energy Center (DAEC) ML18241A3832018-10-31031 October 2018 Issuance of Amendment 307 to Revise Technical Specifications to Adopt TSTF-551, Revision 3 ML18179A1842018-08-16016 August 2018 Issuance of Amendment 306 to Revise Technical Specification 3.5.1, ECCS-Operating ML18081A0742018-05-0707 May 2018 Correction of Error to Implementation Date Associated with License Amendment No 303 ML18016A6272018-03-0909 March 2018 Issuance of License Amendment No. 304 Revision to Technical Specification 3.1.2, Reactor Anomalies ML18011A0592018-03-0707 March 2018 Issuance of License Amendment No. 303 Revision to Technical Specification Table 3.3.2.1-1, Control Rod Block Instrumentation ML18032A4832018-03-0101 March 2018 Correction of Errors in Safety Evaluation Associated with License Amendment No. 301 ML17212A6462017-10-18018 October 2017 Issuance of Amendment to Modify the Plume Exposure Pathway Emergency Planning Zone Boundary ML17220A0262017-09-21021 September 2017 Issuance of Amendment 301 to Revise Emergency Plan ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17072A2322017-03-30030 March 2017 Issuance of Amendment to Revise Technical Specifications Fuel Storage Requirements ML16263A2452016-10-17017 October 2016 Issuance of Amendment to Technical Specifications Section 5.5.6 for the Inservice Testing Program ML16211A5142016-09-12012 September 2016 Issuance of Amendment to Revise Technical Specifications 2.1.1.2, Safety Limit Minimum Critical Power Ratio ML16210A0082016-08-30030 August 2016 Issuance of Amendment to Extend Containment Leakage Test Frequency ML16153A0912016-08-18018 August 2016 Issuance of Amendment to Revise the Value of Reactor Steam Dome Pressure ML16180A0862016-07-25025 July 2016 Issuance of Amendment to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report ML16174A2812016-07-13013 July 2016 Issuance of Amendment (TSCR-154) to Correct Examples in Technical Specifications Section 1.4, Frequency ML15310A0822015-12-22022 December 2015 Issuance of Amendment to Adopt Technical Specifications Task Force (TSTF)-501, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML15169A2612015-08-18018 August 2015 Issuance of Amendment Concerning Extension of Cyber Security Plan Milestone 8 Completion Date ML15014A2002015-02-10010 February 2015 Issuance of Amendment to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523 Generic Letter 2008-01, Managing Gas Accumulation (Tac No. MF4358) ML13301A7052013-11-27027 November 2013 Issuance of Amendment Adopting TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. ML13192A4232013-10-0707 October 2013 Issuance of Amendment to Change Renewed Facility Operating License Condition C.12 ML13210A4492013-09-10010 September 2013 Issuance of Amendment Regarding Transition to a Risk-Informed Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML13189A0712013-07-25025 July 2013 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-522 ML12321A2662012-11-28028 November 2012 Issuance of Amendment Revised Cyber Security Plan Implementation Schedule Milestone 6 ML12249A3172012-09-27027 September 2012 Issuance of Amendment One-Time Technical Specification Change Regarding Core Spray Operability During Shutdown ML1219803602012-08-27027 August 2012 Issuance of Amendment Technical Specification Changes Regarding Alternative Testing of Safety/Relief Valves ML12125A3152012-06-0101 June 2012 Issuance of Amendment Concerning Approval of Upgrade of Emergency Action Level Scheme ML1201102822012-02-24024 February 2012 Issuance of Amendment Adoption of Technical Specifications Task Force Traveler (TSTF-425) to Relocate Specific Surveillance Frequencies to a Licensee-Controlled Program ML1115202312011-09-0808 September 2011 Issuance of Amendment Pertaining to Deletion of Decommissioning Funding Parent Guarantee License Condition ML1119402242011-07-29029 July 2011 Issuance of Amendment Pertaining to Cyber Security Plan (TAC No. 4287) ML1104104552011-02-28028 February 2011 Issuance of Amendment Pertaining to Technical Specification Changes to Add LCO 3.0.9 on the Unavailability of Barriers (TSTF-427) ML1029305862010-12-16016 December 2010 Nextera Energy Duane Arnold, LLC Central Iowa Power Cooperative Corn Belt Power Cooperative, Duane Arnold Energy Center Renewed Facility Operating License ML0530503092010-12-16016 December 2010 Current Facility Operating License DPR-49, Tech Specs, Revised 03/17/2018 ML1029305242010-12-16016 December 2010 Issuance of Renewed Facility Operating License No. DPR-49 for Duane Arnold Energy ML1006211692010-03-31031 March 2010 License Amendment, Issuance of Amendment Pertaining to Changes to Technical Specifications 5.5.12 (Primary Containment Leakage Rate Testing Program) & 3.6.1.3 (Primary Containment Isolation Values), Associated with Main .. ML0930301132009-11-13013 November 2009 Issuance of Amendment Pertaining to Name Chance of Licensee and Co-Owner ML0919003812009-09-18018 September 2009 Issuance of Amendment Pertaining to Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from Technical Specification 5.2.2 to Support Compliance with 10 CFR Part 26. ML0912605512009-05-15015 May 2009 License Amendment, Revision of the 4160 Volt Bus Undervoltage (Degraded Voltage) Maximum Allowed Value ML0831901082008-12-0303 December 2008 License Amendment, Issuance of Amendment to Change Surveillance Requirements of the Cedar River Depth to Assure Ultimate Heat Sink Operability ML0826908352008-11-0606 November 2008 Issuance of License Amendment Regarding Control Rod Notch Testing Frequency and Clarification of a Frequency Example ML0822601162008-09-0909 September 2008 Issuance of Amendment Regarding License Amendment Request to Remove the Emergency Diesel Generator Surveillance Requirement for Preplanned Preventive Maintenance and Testing 2022-05-20
[Table view] Category:Safety Evaluation
MONTHYEARML24149A2862024-06-12012 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 ML22132A2872022-05-24024 May 2022 ISFSI DQAP Approval Letter ML22089A0492022-05-12012 May 2022 Sfmp Review Letter ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval ML22028A2822022-02-0303 February 2022 Defueled Physical Security Plan License Amendment Approval ML21067A6422021-05-13013 May 2021 Cyber Security License Amendment Approval ML21098A1662021-04-28028 April 2021 PDEP and EAL License Amendment Approval ML21097A1412021-04-13013 April 2021 EP Exemption Issuance Letter and SE ML20225A0002020-08-27027 August 2020 Approval of Quality Assurance Topical Report (FPL-3), Revision 0 (EPID-L-2020-LLQ-0002) ML20184A0032020-07-30030 July 2020 Issuance of Amendment No. 312 Removal of License Condition 2.C.(3), Fire Protection Program ML20134J1042020-07-10010 July 2020 Issuance of Amendment No. 311 to Revise Operating License and Technical Specifications for Permanently Defueled Conditions ML20083G0082020-04-29029 April 2020 Issuance of Amendment No. 310 Changes to the Post-Shutdown Emergency Plan for Duane Arnold Energy Center ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19310C2042020-01-0202 January 2020 Issuance of Amendment No. 309 to Align Technical Specifications Staffing and Administrative Requirements ML19204A2872019-08-28028 August 2019 Approval of a Certified Fuel Handler Training and Retraining Program ML19198A0102019-07-23023 July 2019 Approval of Change in the BWRVIP Integrated Surveillance Program Capsule Test Schedule to Accommodate Early Closure ML19168A1302019-06-21021 June 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4391; EPID No. L-2014-JLD-0039) ML18292A5662018-11-30030 November 2018 Issuance of Amendment 308 to Upgrade Emergency Action Level Scheme for Duane Arnold Energy Center (DAEC) ML18241A3832018-10-31031 October 2018 Issuance of Amendment 307 to Revise Technical Specifications to Adopt TSTF-551, Revision 3 ML18179A1842018-08-16016 August 2018 Issuance of Amendment 306 to Revise Technical Specification 3.5.1, ECCS-Operating ML18192C1832018-07-24024 July 2018 Fifth 10-Year Inservice Relief Request RR-05 ML18145A1942018-06-15015 June 2018 Relief Request No. NDE R017 Fourth Inservice Inspection Interval Duane Arnold Energycenter (EPID-L-2017-LLR-0135) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18053A2092018-04-16016 April 2018 Request for Relief No. 03 Proposed Use of Alternative Requirements for Nozzle Inner Radius and Nozzle-to-Shell Weld Inspection for Fifth Inservice Inspection Interval (CAC No. MF9374; EPID L-2017-LLR-0110) ML18016A6272018-03-0909 March 2018 Issuance of License Amendment No. 304 Revision to Technical Specification 3.1.2, Reactor Anomalies ML18011A0592018-03-0707 March 2018 Issuance of License Amendment No. 303 Revision to Technical Specification Table 3.3.2.1-1, Control Rod Block Instrumentation ML17353A6822018-01-19019 January 2018 Request for Relief No. RR 01, Regarding Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds for the Renewed Operating License Term ML17347A1112018-01-17017 January 2018 Safety Evaluation for Request for Relief from Seal Weld Procedure Qualification, Relief Request No. RR-04 ML17272A0182017-12-19019 December 2017 Relief Request No. RR-02- Proposed Alternative to ASME Code Examination Requirements for Buried Piping Related to Fifth Inservice Inspection Interval Program Plan ML17212A6462017-10-18018 October 2017 Issuance of Amendment to Modify the Plume Exposure Pathway Emergency Planning Zone Boundary ML17220A0262017-09-21021 September 2017 Issuance of Amendment 301 to Revise Emergency Plan ML17129A0372017-05-26026 May 2017 Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrument Related to Orders EA-12-049 and EA-12-051 ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17072A2322017-03-30030 March 2017 Issuance of Amendment to Revise Technical Specifications Fuel Storage Requirements ML16313A4752016-11-30030 November 2016 Correction of Errors in Safety Evaluation Associated with License Amendment No. 298 ML16263A2452016-10-17017 October 2016 Issuance of Amendment to Technical Specifications Section 5.5.6 for the Inservice Testing Program ML16211A5142016-09-12012 September 2016 Issuance of Amendment to Revise Technical Specifications 2.1.1.2, Safety Limit Minimum Critical Power Ratio ML16210A0082016-08-30030 August 2016 Issuance of Amendment to Extend Containment Leakage Test Frequency ML16153A0912016-08-18018 August 2016 Issuance of Amendment to Revise the Value of Reactor Steam Dome Pressure ML16180A0862016-07-25025 July 2016 Issuance of Amendment to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report ML16174A2812016-07-13013 July 2016 Issuance of Amendment (TSCR-154) to Correct Examples in Technical Specifications Section 1.4, Frequency ML16053A4262016-04-29029 April 2016 Correction of Typographical Errors in Safety Evaluation Associated with License Amendment No. 292 ML16008A0862016-01-21021 January 2016 Relief Request No. PR-01, PR-02, VR-01, VR-02, and VR-03 Related to the Inservice Testing Program for the Fifth 10-Year Interval ML15310A0822015-12-22022 December 2015 Issuance of Amendment to Adopt Technical Specifications Task Force (TSTF)-501, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML15169A2612015-08-18018 August 2015 Issuance of Amendment Concerning Extension of Cyber Security Plan Milestone 8 Completion Date ML15014A2002015-02-10010 February 2015 Issuance of Amendment to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523 Generic Letter 2008-01, Managing Gas Accumulation (Tac No. MF4358) ML14144A0022014-06-0909 June 2014 Relief Request No. VR-03 Related to the Inservice Testing Program for the Fourth 10-Year Interval ML14099A3352014-04-29029 April 2014 Relief for 2nd Period Limited Weld Examinations ML13301A7052013-11-27027 November 2013 Issuance of Amendment Adopting TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. 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 2024-06-12
[Table view] |
Text
March 20, 2008 Mr. Richard L. Anderson Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - ISSUANCE OF AMENDMENT REGARDING LICENSE AMENDMENT REQUEST TO IMPROVE THE BANKED POSITION WITHDRAWAL SEQUENCE CONTROL ROD INSERTION PROCESS (TAC NO. MD6814)
Dear Mr. Anderson:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 268 to Facility Operating License No. DPR-49 for the Duane Arnold Energy Center.
This amendment consists of a change to the Technical Specifications (TS) in response to your application dated September 14, 2007, which requested revision to TS 3.3.2.1, Control Rod Block Instrumentation, Table 3.3.2.1-1, Control Rod Block Instrumentation, to modify a footnote such that a new Banked Position Withdrawal Sequence (BPWS) shutdown sequence could be utilized. In conjunction with this change, the TS Bases for Section 3.1.6, Rod Pattern Control, and 3.3.2.1, Control Rod Block Instrumentation, will be revised to reflect the new BPWS shutdown sequence.
A copy of the Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Karl D. Feintuch, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosures:
- 1. Amendment No. 268 to License No. DPR-49
- 2. Safety Evaluation cc w/encls: See next page
ML080530215 Pkg. ML080530236 TS:Ml080810359 OFFICE NRR/ NRR/ NRR/ ITSB/ BC SRXB/ BC SNPB/ BC OGC NRR/
LPL3-1/PM LPL3-1/LA LPL3-1/ LA LPL3-1/BC NAME KFeintuch BTully THarris GMWaig GCranston AMendiola RHolmes/N LJames LO DATE 02 / 28 /08 03 / 06 /08 03 / 06 /08 03 / 06 /08 03 / 05 /08 03 / 05 /08 03 / 17 /08 03 / 20 /08 Duane Arnold Energy Center cc: Mr. Mano Nazar Senior Vice President Mr. J. A. Stall and Nuclear Chief Operating Officer Senior Vice President, Nuclear and Chief Florida Power & Light Company Nuclear Officer P. O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408 P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. D. A. Curtland Plant Manager Mr. M. S. Ross Duane Arnold Energy Center Managing Attorney 3277 DAEC Rd.
Florida Power & Light Company Palo, IA 52324-9785 P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. R. S. Kundalkar Vice President, Nuclear Technical Svcs.
Ms. Marjan Mashhadi Florida Power & Light Company Senior Attorney P. O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408 801 Pennsylvania Avenue, NW Suite 220 Daniel K. McGhee Washington, DC 20004 Iowa Department of Public Health Bureau of Radiological Health Don E. Grissette 321 East 12th Street Vice President, Nuclear Training and Lucas State Office Building, 5th Floor Performance Improvement Des Moines, IA 50319-0075 Florida Power & Light Company P. O. Box 14000 Chairman, Linn County Juno Beach, FL 33408 Board of Supervisors 930 1st Street SW John Bjorseth Cedar Rapids, IA 52404 Site Director Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 Steven R. Catron Manager, Regulatory Affairs December 12, 2007 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
FPL ENERGY DUANE ARNOLD, LLC DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 268 License No. DPR-49
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by FPL Energy Duane Arnold, LLC dated September 14, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 268, are hereby incorporated in the license. FPL shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Lois James, Branch Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: March 20, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 268 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the License and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT License Page 3 License Page 3 TS Page 3.3-20 TS Page 3.3-20
2.B.(2) FPL Energy Duane Arnold, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended as of June 1992 and as supplemented by letters dated March 26, 1993, and November 17, 2000.
2.B.(3) FPL Energy Duane Arnold, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; 2.B.(4) FPL Energy Duane Arnold, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated radioactive apparatus components; 2.B.(5) FPL Energy Duane Arnold, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
Maximum Power Level 2.C.(1) FPL Energy Duane Arnold, LLC is authorized to operate the Duane Arnold Energy Center at steady state reactor core power levels not in excess of 1912 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 268, are hereby incorporated in the license. FPL Energy Duane Arnold, LLC shall operate the facility in accordance with the Technical Specifications.
Amendment No. 268
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 268 TO FACILITY OPERATING LICENSE NO. DPR-49 FPL ENERGY DUANE ARNOLD, LLC DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331
1.0 INTRODUCTION
By letter to the Nuclear Regulatory Commission (NRC) dated September 14, 2007, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072681088), FPL Energy Duane Arnold, LLC (the licensee) proposed changes to the technical specifications (TS) for Duane Arnold Energy Center (DAEC). The requested changes are the adoption of TSTF-476, Revision 1, Improved BPWS Control Rod Insertion Process (NEDO-33091-A), to the Boiling-Water Reactor (BWR) Standard Technical Specifications (STS), which was proposed by the Technical Specifications Task Force (TSTF) by letter on January 9, 2007 (ADAMS Accession No. ML070090561) and approved by the NRC (72 FR 29004, May 23, 2007). This TSTF involves changes to NUREG-1433 and NUREG-1434 Section 3.1.6 Rod Pattern Control, Section 3.3.2.1 Control Rod Block Instrumentation, and Table 3.3.2.1-1. The proposed TSTF would allow the use of the improved banked position withdrawal sequence (BPWS) during shutdowns if the conditions of NEDO-33091-A, Revision 2, Improved BPWS Control Rod Insertion Process, dated July 2004, have been satisfied.
2.0 REGULATORY EVALUATION
10 CFR Part 50 includes the NRCs requirement that TSs shall be included by applicants for a license authorizing operation of a production or utilization facility. 10 CFR 50.36 (d) requires that TSs include items in five specific categories. These categories are: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operations (LCOs);
(3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. For this licensing action the proposed change to TS Section 3.3, Table 3.3.2.1-1 affects categories (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; and (3) SRs.
The control rod drop accident (CRDA) is the design-basis accident for the subject TS changes.
In order to minimize the impact of a CRDA, the BPWS process was developed to minimize control rod reactivity worth for BWR plants. The proposed improved BPWS further simplifies the control rod insertion process, and in order to evaluate it, the staff followed the guidelines of Standard Review Plan Section 15.4.9, and referred to General Design Criterion (GDC) 28 of Appendix A to 10 CFR Part 50 as its regulatory requirement. GDC 28 states that the reactivity control systems shall be designed with appropriate limits on the potential amount and rate of reactivity increase to assure that the effects of postulated reactivity accidents can neither (1) result in damage to the reactor coolant pressure boundary greater than limited local yielding nor (2) sufficiently disturb the core, its support structures or other reactor pressure vessel internals to impair significantly the capability to cool the core.
3.0 TECHNICAL EVALUATION
In its safety evaluation for Licensing Topical Report NEDO-33091-A, Improved BPWS Control Rod Insertion Process, dated June 16, 2004, ADAMS Accession No. ML041700479, the NRC staff determined that the methodology described in TSTF-476, Revision 1, to incorporate the improved BPWS into the STS, is acceptable.
TSTF-476, Revision 1 states that the improved BPWS provides the following benefits: (1) allows the plant to reach the all-rods-in condition prior to significant reactor cool down, which reduces the potential for re-criticality as the reactor cools down; (2) reduces the potential for an operator reactivity control error by reducing the total number of control rod manipulations; (3) minimizes the need for manual scrams during plant shutdowns, resulting in less wear on control rod drive (CRD) system components and CRD mechanisms; and, (4) eliminates unnecessary control rod manipulations at low power, resulting in less wear on reactor manual control and CRD system components.
The safety evaluation for NEDO-33091-A explained that the potential for the CRDA will be eliminated by the following changes to operational procedures, which DAEC has committed to and stated, in its application letter dated September 14, 2007, that it has made:
- 1. Before reducing power to the low-power set point (LPSP), operators shall confirm control rod coupling integrity for all rods that are fully withdrawn. Control rods that have not been confirmed coupled and are in intermediate positions, must be fully inserted prior to power reduction to the LPSP. No action is required for fully-inserted control rods.
If a shutdown is required and all rods, which are not confirmed coupled, cannot be fully inserted prior to power dropping below the LPSP, then the original/standard BPWS must be adhered to.
- 2. After reactor power drops below the LPSP, rods may be inserted from notch position 48 to notch position 00 without stopping at the intermediate positions. However, GE Nuclear Energy recommends that operators insert rods in the same order as specified for the original/standard BPWS as much as reasonably possible. If a plant is in the process of shutting down following improved BPWS with the power below the LPSP, no control rod shall be withdrawn unless the control rod pattern is in compliance with standard BPWS requirements.
In addition to the procedure changes specified above, the staff previously verified during its review of NEDO-33091-A, Revision 2 that no single failure of the BWR CRD mechanical or hydraulic system can cause a control rod to drop completely out of the reactor core during the shutdown process. Therefore, the proper use of the improved BPWS will prevent a CRDA from occurring while power is below the LPSP.
The NRC staff finds the proposed TS change in DAECs amendment request properly incorporates the improved BPWS procedure into the STS, and that DAEC accurately adopted TSTF-476 and the requisite procedural changes. Therefore, the NRC staff approves the DAEC license amendment request to adopt TSTF-476, Revision 1.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Iowa State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
S The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes a surveillance requirement. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (72 FR 68216). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: A. Jason Lising, NRR Date: March 20, 2008