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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
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NEXTera ENERGYP July 24, 2014 NG-14-0187 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No. 50-331 Renewed Op. License No. DPR-49 Response to Request for Additional Information, Application for Technical Specification Change Regarding Battery Terminal and Charger Voltage and Amperage
References:
- 1) License Amendment Request (TSCR-145):
Application for Technical Specification Change Regarding Battery Terminal and Charger Voltage and Amperage, NG-1 3-0297, dated August 29, 2013 (ML13247A275)
- 2) Electronic Communication, Duane Arnold -LAR -TS Change regarding Battery Terminal and Charger Voltage and Amperage -Request for Additional Information
-MF2763, dated April 24, 2014 3) Response to Request for Additional Information, Application for Technical Specification Change Regarding Battery Terminal and Charger Voltage and Amperage, NG-14-0140, dated May 28, 2014 (ML In the Reference 1 letter, NextEra Energy Duane Arnold, LLC (hereafter NextEra Energy Duane Arnold) submitted a License Amendment Request for the Duane Arnold Energy Center (DAEC) pursuant to 10 CFR 50.90. Subsequently, the NRC Staff requested, via Reference 2, additional information regarding that application.
In Reference 3, NextEra Energy Duane Arnold committed to transmitting additional manufacturer information.
The Enclosure to this letter contains the requested information.
A I NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324 Document Control Desk NG-14-0187 Page 2 of 2 This additional information does not impact the 10 CFR 50.92 evaluation of "No Significant Hazards Consideration" previously provided in the referenced application.
This letter does not make any new commitments or changes to existing commitments.
If you have any questions or require additional information, please contact J. Michael Davis at 319-851-7032.
I declare under penalty of perjury that the foregoing is true and correct.Executed on July 24, 2014 Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC Enclosure cc: NRC Regional Administrator NRC Resident Inspector NRC Project Manager A. Leek (State of Iowa)
Enclosure 1 to NG-14-0187 Response to Request for Additional Information, Application for Technical Specification Chanae Reaardina Battery Terminal and Charaer Voltaae and Amoeraae 1 page follows Response to Request for Additional Information, Application for Technical Specification Change Regarding Battery Terminal and Charger Voltage and Amperage As indicated in the attached letter from the Battery Cell Manufacturer, C&D Technologies, Inc., the impacts of equalizing the batteries at 137-137.5 volts are as follows:* The time required for completing a recharge would be extended.Since the DAEC only discharges the batteries during extended/refuel outages the equalization/recharge portion of the testing procedures and the equalization will continue until the batteries are properly charged.* There would be limited mixing of the electrolyte.
As stated above the equalization/recharge portion of the testing procedures and the equalization will continue until the batteries are properly charged. All of the individual cell voltages and specific gravities are verified before the battery is placed back on float charge." If there are extended temperature excursions "well below" 770 F, a low equalizing charge can become just a standard recharge voltage with possible undercharge effects if the charge is not maintained long enough.Again, as stated above the equalization/recharge portion of the testing procedures and the equalization will continue until the batteries are properly charged. In addition, the DAEC battery rooms are located in interior rooms of our control building, with no exterior walls such that a temperature excursion "well below" 770 F is not realistic.
The letter from the manufacturer does not indicate that the lower equalizing voltage will damage the cells in any way, only that the lower voltages will cause the equalization/recharge period to take longer. The DAEC therefore believes that the lower equalizing voltages will not damage nor have a detrimental effect on the batteries as long as we maintain the charge long enough to ensure full equalization.
Page 1 Enclosure 2 to NG-14-0187 Manufacturer's Letter L. Carson to D. Pint, dated July 9, 2014 1 page follows CmTECHNOLOGIES, INC.Power Solutions 1400 Union Meeting Road Blue Bell, PA 19422 Phone: (215) 775-1314 Fax: (215) 619-7887 Sent via Email to: Dennis.PintcNEE.com July 9, 2014 Mr. Dennis Pint Duane Arnold Energy Center NextEra Energy Resources
Subject:
Battery Equalizing Voltages
Dear Dennis:
You advised us that you intend to add 2 cells your 58-cell station battery strings. You will be able to float the battery strings in the 132.5 to 133.5 V range (2.208 to 2.225 volts per cell). This will allow the cells to float within the low end of the recommended range of 2.20 to 2.25 volts per cell, based on an ambient temperature of 77 0 F.For equalizing charge, you advised that the available range will be 137 to 137.5 volts (2.283 to 2.292 volts per cell). This is below the recommended equalizing charge voltage range of 2.33 to 2.38 volts per cell, so you requested if there would be any detrimental effects.As we discussed, the time required for completing a recharge would be extended when the voltage is limited to 2.29 volts per cell. In addition, there would be limited mixing of the electrolyte, since gassing at that voltage is very light and it would take a long time for the specific gravity reading to be representative of the strength of the electrolyte.
Another concern is that if there are extended temperature excursions that are well below 770F, a low equalize charge can become just a standard recharge voltage with possible undercharge effects if the charge is not maintained long enough.Other than these issues, we would not expect the batteries to be damaged by this practice.Regards, Larry A. Carson Utility & Nuclear Product Manager