Letter Sequence Approval |
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TAC:MD0293, Use of TS 3.10.1 for SCRAM Time Testing Activities (Approved, Closed) |
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MONTHYEARNG-06-0250, Technical Specification Change Request (TSCR-078): Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities, Affected Technical Specifications: Section 3.10.12006-03-0101 March 2006 Technical Specification Change Request (TSCR-078): Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities, Affected Technical Specifications: Section 3.10.1 Project stage: Other ML0619906342006-07-24024 July 2006 RAI, Proposed Amendment to Revise the Limiting Condition for Operation 3.10.1 Project stage: RAI NG-06-0516, Response to Request for Additional Information Related to Proposed Amendment to Revise Limiting Condition for Operation 3.10.12006-08-17017 August 2006 Response to Request for Additional Information Related to Proposed Amendment to Revise Limiting Condition for Operation 3.10.1 Project stage: Response to RAI ML0629903782006-11-0202 November 2006 TSTF-484 LAR SE Project stage: Other ML0703804842007-02-0505 February 2007 Technical Specification, System Leakage and Hydrostatic Testing Operation Project stage: Other ML0635204082007-02-0505 February 2007 Issuance of Amendment, System Leakage and Hydrostatic Testing Operation Project stage: Approval 2006-07-24
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Category:Letter
MONTHYEARL-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-22-0050, 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 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 ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval 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 NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22028A2822022-02-0303 February 2022 Defueled Physical Security Plan License Amendment Approval ML22033A0802022-02-0202 February 2022 Supplement to License Amendment Request (TSCR-188): Proposed Change to the Physical Security Plan for the Post-Shutdown and Permanently Defueled Condition IR 05000331/20210012022-01-25025 January 2022 NRC Inspection Report Nos. 05000331/2021001(DNMS); 07200032/2021001(DNMS); and 07200032/2021002(DNMS) - Duane Arnold Energy Center ML21172A2172022-01-21021 January 2022 Issuance of License Amendment to Adopt ISFSI-Only Technical Specifications NG-22-0009, Registration of Independent Spent Fuel Installation Storage Casks2022-01-20020 January 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0001, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister2022-01-0606 January 2022 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister NG-21-0038, Registration of Independent Spent Fuel Installation Storage Casks2021-12-22022 December 2021 Registration of Independent Spent Fuel Installation Storage Casks NG-21-0035, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-12-10010 December 2021 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister 2024-01-25
[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
MONTHYEARML22132A2872022-05-24024 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 ML13192A4232013-10-0707 October 2013 Issuance of Amendment to Change Renewed Facility Operating License Condition C.12 2022-05-24
[Table view] |
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February 5, 2007Mr. Gary Van MiddlesworthVice President Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - ISSUANCE OF AMENDMENT RE: SYSTEM LEAKAGE AND HYDROSTATIC TESTING OPERATION (TAC NO. MD0293)
Dear Mr. Van Middlesworth:
The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosedAmendment No. 264 to Facility Operating License No. DPR-49 for the Duane Arnold Energy Center. The amendment consists of changes to the Technical Specifications (TSs) inresponse to your application dated March 1, 2006, as supplemented by letter dated August 17, 2006.The amendment modifies Special Operations Limiting Condition for Operation (LCO) 3.10.1,"System Leakage and Hydrostatic Testing Operation," to allow more efficient testing during a refueling outage. Specifically, the LCO 3.10.1 allowance for operation with the average reactor coolant temperature greater than 212 F (while considering operational conditions to be inMode 4), is extended to include operations where temperature exceeds 212 F: (1) as aconsequence of maintaining adequate reactor pressure for a system leakage or hydrostatic test; or (2) as a consequence of maintaining adequate reactor pressure for control rod scram time testing initiated in conjunction with a system leakage or hydrostatic test. This change is based on the NRC-approved Technical Specification Task Force (TSTF) standard TS change TSTF-484, Revision 0. A copy of the Safety Evaluation is also enclosed. A Notice of Issuance will be included in theCommission's next biweekly Federal Register notice.Sincerely,/RA/Richard B. Ennis, Senior Project ManagerPlant Licensing Branch III-1 Division of Licensing Project Management Office of Nuclear Reactor RegulationDocket No. 50-331
Enclosures:
- 1. Amendment No. 264 to License No. DPR-49
- 2. Safety Evaluationcc w/encls: See next page
ML063520408Package: ML063520420TS: ML070380484 OFFICELPL3-1/PMLPL3-1/LAITSB/BCOGCLPL3-1/BC (A)NAMEREnnisTHarrisTKobetzJRundMilano for LRaghavanDATE1/4/071/5/071/8/071/12/072/5/07 cc:Mr. J. A. Stall Senior 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 FPL ENERGY DUANE ARNOLD, LLCDOCKET NO. 50-331DUANE ARNOLD ENERGY CENTERAMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 264 License No. DPR-491. The U.S. Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by FPL Energy Duane Arnold, LLC March 1,2006, as supplemented by letter dated August 17, 2006, 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment 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 andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated 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. 264, are hereby incorporated in the license. FPL Energy Duane Arnold, LLC 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 implementedwithin 30 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/L. Raghavan, ChiefPlant 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: February 5, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 264FACILITY OPERATING LICENSE NO. DPR-49DOCKET NO. 50-331Replace the following page of the Facility Operating License No. DPR-49 with the attachedrevised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.REMOVEINSERTPage 3Page 3Replace the following page of the Appendix A, Technical Specifications with the attachedrevised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.REMOVEINSERT3.10-13.10-1 2.B.(2)FPL Energy Duane Arnold, LLC, pursuant to the Act and 10 CFR Part 70, toreceive, 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, 40and 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, 40and 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 and70, 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 thefollowing 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 Level2.C.(1)FPL Energy Duane Arnold, LLC is authorized to operate the Duane ArnoldEnergy Center at steady state reactor core power levels not in excess of 1912 megawatts (thermal). (2)Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 264, are hereby incorporated in the license. FPL Energy Duane Arnold, LLC shall operate the facility in accordance with the Technical Specifications.Amendment No. 264 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 264 TO FACILITY OPERATING LICENSE NO. DPR-49FPL ENERGY DUANE ARNOLD, LLCDUANE ARNOLD ENERGY CENTERDOCKET NO. 50-33
11.0INTRODUCTION
By application dated March 1, 2006, as supplemented by letter dated August 17, 2006, FPLEnergy Duane Arnold, LLC (the licensee) requested changes to the Technical Specifications (TSs) for the Duane Arnold Energy Center (DAEC). The proposed amendment would modify Special Operations Limiting Condition for Operation(LCO) 3.10.1, "System Leakage and Hydrostatic Testing Operation," to allow more efficient testing during a refueling outage. Specifically, the LCO 3.10.1 allowance for operation with the average reactor coolant temperature greater than 212 F (while considering operationalconditions to be in Mode 4), would be extended to include operations where temperature exceeds 212 F: (1) as a consequence of maintaining adequate reactor pressure for a systemleakage or hydrostatic test; or (2) as a consequence of maintaining adequate reactor pressure for control rod scram time testing initiated in conjunction with a system leakage or hydrostatic test. The DAEC proposed amendment is based on Technical Specification Task Force (TSTF)change traveler TSTF-484, Revision 0, "Use of TS 3.10.1 for Scram Time Testing Activities,"
which has been approved generically for the Standard Technical Specifications (STS) by the Nuclear Regulatory Commission (NRC or the Commission). A notice announcing the availability of a model application for TSTF-484 using the consolidated line item improvement process (CLIIP) was published by the NRC staff in the Federal Register on November 27, 2006(71 FR 68642). In addition, a model Safety Evaluation (SE) and no significant hazards determination for TSTF-484 was published by the NRC staff in the Federal Register onOctober 27, 2006 (71 FR 63050). Sections 2.0 and 3.0 of this SE are based on the TSTF-484 model SE with minor editorial changes and changes to reflect the following differences between the DAEC TSs and the STS:1)DAEC TS Table 1.1-1, "MODES," defines Mode 4, "Cold Shutdown," as pertaining to plantconditions when the average reactor coolant temperature is less than or equal to 212 F. The STS that form the basis for TSTF-484 (NUREG-1433, Revision 3, and NUREG-1434, Revision 3) define Mode 4 as pertaining to plant conditions when the average reactor coolant temperature is less than or equal to 200 F. The STS show the 200 F value in brackets indicating that the value is plant-specific. As such, Sections 2.0 and 3.0 of this SEhave been modified accordingly to differentiate between the STS and the DAEC TSs.2)Section 2.2 , "Control Rod Scram Time Testing," of the TSTF-484 model SE discusses STSsurveillance requirements (SRs) 3.1.4.1 and 3.1.4.4. The DAEC TS format, cross references and nomenclature is slightly different than the STS. DAEC SRs 3.1.4.1 and 3.1.4.2 are equivalent to STS SRs 3.1.4.1 and 3.1.4.4. As such, Sections 2.0 and 3.0 of this SE have been modified accordingly to differentiate between the STS and the DAEC TSs.The supplement dated August 17, 2006, provided additional information that clarified theapplication, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register on December 5, 2006 (71 FR 70560).
2.0REGULATORY EVALUATION
2.1Inservice Leak and Hydrostatic TestingThe Reactor Coolant System (RCS) serves as a pressure boundary and also serves to providea flow path for the circulation of coolant past the fuel. In order to maintain RCS integrity,Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) requires periodic hydrostatic and leakage testing. Hydrostatic tests are required to be performed once every 10 years and leakage tests are required to be performed each refueling outage. Appendix G to Title 10 of the Code of Federal Regulations (10 CFR) Part 50states that pressure tests and leak tests of the reactor vessel that are required by Section XI of the ASME Code must be completed before the core is critical.NUREG-1433, Revision 3, "Standard Technical Specifications General Electric Plants, BWR/4"and NUREG-1434, Revision 3, "Standard Technical Specifications General Electric Plants, BWR/6" both currently contain LCO 3.10.1, "Inservice Leak and Hydrostatic Testing Operation."
LCO 3.10.1 was created to allow for hydrostatic and leakage testing to be conducted while in Mode 4 with average reactor coolant temperature greater than the temperature limit specified in TS Table 1.1-1 for Mode 4, provided certain secondary containment LCOs are met. TSTF-484 modifies LCO 3.10.1 to allow a licensee to implement LCO 3.10.1, while hydrostaticand leakage testing is being conducted, should average reactor coolant temperature exceed the Mode 4 temperature limit during testing. This modification does not alter current requirements for hydrostatic and leakage testing as required by Appendix G to 10 CFR Part 50.2.2Control Rod Scram Time TestingControl rods function to control reactor power level and to provide adequate excess negativereactivity to shut down the reactor from any normal operating or accident condition at any time during core life. The control rods are scrammed by using hydraulic pressure exerted by the control rod drive (CRD) system. Criterion 10 of Appendix A to 10 CFR Part 50 states that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. The scram reactivity used in design-basis accidents and transient analyses is based on an assumedcontrol rod scram time.NUREG-1433 and NUREG-1434 both currently contain SRs to conduct scram time testingwhen certain conditions are met in order to ensure that Criterion 10 of Appendix A to 10 CFR Part 50 is satisfied (STS SRs 3.1.4.1 and 3.1.4.4). SR 3.1.4.1 requires scram time testing to be conducted following a shutdown greater than 120 days while SR 3.1.4.4 requires scram time testing to be conducted following work on the CRD system or following fuel movement within the affected core cell. Both SRs must be performed at reactor steam dome pressure greater than or equal to 800 psig and prior to exceeding 40 percent rated thermal power (RTP).For DAEC, adoption of TSTF-484 would modify LCO 3.10.1 to allow SRs 3.1.4.1 and 3.1.4.2 tobe conducted in Mode 4 with average reactor coolant temperature greater than 212 F. Scramtime testing would be performed in accordance with LCO 3.10.4, "Single Control Rod Withdrawal - Cold Shutdown." This modification to LCO 3.10.1 does not alter the means of compliance with Criterion 10 of Appendix A to 10 CFR Part 50.
3.0TECHNICAL EVALUATION
For DAEC, the existing provisions of LCO 3.10.1 allow for hydrostatic and leakage testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212 F, whileimposing Mode 3 secondary containment requirements. Under the existing provision, LCO 3.10.1 would have to be implemented prior to hydrostatic and leakage testing. As a result, if LCO 3.10.1 was not implemented prior to hydrostatic and leakage testing, hydrostatic and leakage testing would have to be terminated if average reactor coolant temperature exceeded
212 F during the conduct of the hydrostatic and leakage test. For DAEC, adoption of TSTF-484 would modify LCO 3.10.1 to allow the licensee to implement LCO 3.10.1, while hydrostatic and leakage testing is being conducted, should average reactor coolant temperature exceed 212 F during testing. The modification will allow completion of testingwithout the potential for interrupting the test in order to reduce reactor vessel pressure, cool the RCS, and restart the test below 212 F. Since the current LCO 3.10.1 allows testing to beconducted while in Mode 4 with average reactor coolant temperature greater than 212 F, theproposed change does not introduce any new operational conditions beyond those currently allowed. DAEC SRs 3.1.4.1 and 3.1.4.2 require that control rod scram time be tested at reactor steamdome pressure greater than or equal to 800 psig and before exceeding 40 percent rated thermal power (RTP). Performance of control rod scram time testing is typically scheduled concurrent with inservice leak or hydrostatic testing while the RCS is pressurized. Because of the number of control rods that must be tested, it is possible for the inservice leak or hydrostatic test to be completed prior to completing the scram time test. Under existing provisions, if scram time testing can not be completed during the LCO 3.10.1 inservice leak or hydrostatic test, scram time testing must be suspended. Additionally, if LCO 3.10.1 is not implemented and average reactor coolant temperature exceeds 212 F while performing the scram time test,scram time testing must also be suspended. In both situations, scram time testing is resumed during startup and is completed prior to exceeding 40 percent RTP. TSTF-484 modifies LCO 3.10.1 to allow a licensee to complete scram time testing initiated during inservice leak or hydrostatic testing. As stated earlier, since the current LCO 3.10.1 allows testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212 F, the proposed change does not introduce any new operational conditions beyond those currentlyallowed. Completion of scram time testing prior to reactor criticality and power operations results in a more conservative operating philosophy with attendant potential safety benefits.It is acceptable to perform other testing concurrent with the inservice leak or hydrostatic testprovided that this testing can be performed safely and does not interfere with the leak or hydrostatic test. However, it is not permissible to remain in TS 3.10.1 solely to complete such testing following the completion of inservice leak or hydrostatic testing and scram time testing.Since the tests are performed with the reactor pressure vessel (RPV) nearly water solid, at lowdecay heat values, and near Mode 4 conditions, the stored energy in the reactor core will be very low. Small leaks from the RCS would be detected by inspections before a significant loss of inventory occurred. In addition, two low-pressure emergency core cooling systems (ECCS) injection/spray subsystems are required to be operable in Mode 4 by TS 3.5.2, "ECCS-Shutdown." In the event of a large RCS leak, the RPV would rapidly depressurize and allow operation of the low pressure ECCS. The capability of the low pressure ECCS would be adequate to maintain the fuel covered under the low decay heat conditions during these tests.
Also, LCO 3.10.1 requires that secondary containment and standby gas treatment system be operable and capable of handling any airborne radioactivity or steam leaks that may occur during performance of testing. The protection provided by the normally required Mode 4 applicable LCOs, in addition to thesecondary containment requirements required to be met by LCO 3.10.1, minimizes potential consequences in the event of any postulated abnormal event during testing. In addition, the requested modification to LCO 3.10.1 does not create any new modes of operation or operating conditions that are not currently allowed. Therefore, the NRC staff finds the proposed change acceptable.The licensee stated that the TS Bases would also be changed (under the TS Bases ControlProgram specified in TS 5.5.10) to reflect the changes to LCO 3.10.1. The NRC staff considered the proposed TS Bases changes as information only. The NRC staff did not review or make a finding with respect to these changes.
4.0STATE CONSULTATION
In accordance with the Commission's regulations, the Iowa State official was notified of theproposed issuance of the amendment. The State official had no comments.
5.0ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. TheCommission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 70560). 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 theissuance of the amendment.
6.0CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) thereis 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.
7.0REFERENCES
1.NUREG-1433, Revision 3, "Standard Technical Specifications General Electric Plants,BWR/4."2.NUREG-1434, Revision 3, "Standard Technical Specifications General Electric Plants,BWR/6."3.Request for Additional Information (RAI) Regarding TSTF-484, April, 7, 2006 (ADAMSAccession No. ML060970568). 4.Response to NRC RAIs Regarding TSTF-484, June 5, 2006 (ADAMS Accession No.ML061560523).5.TSTF-484 Revision 0, "Use of TS 3.10.1 for Scram Times Testing Activities", May 5,2005 (ADAMS Accession No. ML052930102).6.TSTF Response to NRC Notice for Comment, September 20, 2006, (ADAMS AccessionNo. ML062650171). Principal Contributors: A. Lewin R. Ennis Date: February 5, 2007