Letter Sequence Response to RAI |
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Category:Letter type:NG
MONTHYEARNG-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 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 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 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 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 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 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 NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022 Registration of Independent Spent Fuel Installation Storage Casks 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 NG-21-0030, Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-10-21021 October 2021 Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister NG-21-0028, Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 02021-07-30030 July 2021 Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 0 NG-21-0010, License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2021-06-28028 June 2021 License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme NG-21-0026, CFR 72.48 Report of Changes. Tests. and Experiments2021-06-16016 June 2021 CFR 72.48 Report of Changes. Tests. and Experiments NG-21-0011, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0404 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NG-21-0009, Report of Facility Changes. Tests and Experiments. and Commitment Changes2021-04-27027 April 2021 Report of Facility Changes. Tests and Experiments. and Commitment Changes NG-21-0021, Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements2021-04-22022 April 2021 Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements NG-21-0006, 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report2021-03-31031 March 2021 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-21-0005, NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 02021-03-29029 March 2021 NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 0 NG-20-0094, License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool2021-02-19019 February 2021 License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool NG-21-0004, Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report2021-02-0505 February 2021 Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report NG-20-0078, Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb)2021-01-13013 January 2021 Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb) NG-20-0101, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic2020-12-29029 December 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic NG-20-0099, Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-12-0101 December 2020 Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0093, Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-10-29029 October 2020 Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0090, Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center2020-10-12012 October 2020 Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center NG-20-0083, Registration of Independent Spent Fuel Installation Storage Casks2020-10-12012 October 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0069, Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2020-10-0707 October 2020 Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E NG-20-0082, Registration of Independent Spent Fuel Installation Storage Casks2020-09-28028 September 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0071, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic NG-20-0077, Registration of Independent Spent Fuel Installation Storage Casks2020-09-10010 September 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0073, Notice Regarding Proposed Amendment to Decommissioning Trust Agreements2020-09-0101 September 2020 Notice Regarding Proposed Amendment to Decommissioning Trust Agreements NG-20-0074, Certification of Permanent Cessation of Power Operations2020-08-27027 August 2020 Certification of Permanent Cessation of Power Operations NG-20-0067, Registration of Independent Spent Fuel Installation Storage Casks2020-08-12012 August 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0035, Request for Exemption from 10 CFR 50.54(w)(1)2020-07-16016 July 2020 Request for Exemption from 10 CFR 50.54(w)(1) 2023-05-23
[Table view] Category:Technical Specifications
MONTHYEARML21067A6422021-05-13013 May 2021 Cyber Security License Amendment Approval ML19310C2042020-01-0202 January 2020 Issuance of Amendment No. 309 to Align Technical Specifications Staffing and Administrative Requirements NG-18-0041, Correction of Error in Final Technical Specification Page 1.1-3 for License Amendment Request (TSCR-168), Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-03-28028 March 2018 Correction of Error in Final Technical Specification Page 1.1-3 for License Amendment Request (TSCR-168), Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control NG-17-0233, Submittal of License Amendment Request (TSCR-178) Application to Reduce the Required Number of Operable Suppression Chamber-to-Drywell Vacuum Breakers2017-12-15015 December 2017 Submittal of License Amendment Request (TSCR-178) Application to Reduce the Required Number of Operable Suppression Chamber-to-Drywell Vacuum Breakers 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) NG-14-0143, License Amendment Request (TSCR-146): Application to Revise Tech Specs to Adopt Technical Specifications Task Force (TSTF) Traveler-523,Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Proces2014-06-23023 June 2014 License Amendment Request (TSCR-146): Application to Revise Tech Specs to Adopt Technical Specifications Task Force (TSTF) Traveler-523,Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process NG-13-0297, License Amendment Request (TSCR-145): Application for Technical Specification Change Regarding Battery Terminal and Charger Voltage and Amperage Section Affected: 3.8.42013-08-29029 August 2013 License Amendment Request (TSCR-145): Application for Technical Specification Change Regarding Battery Terminal and Charger Voltage and Amperage Section Affected: 3.8.4 NG-12-0434, Technical Specification Change Request (TSCR-141): License Amendment Request for Change to Renewed Operating License Condition C.122012-11-13013 November 2012 Technical Specification Change Request (TSCR-141): License Amendment Request for Change to Renewed Operating License Condition C.12 NG-12-0256, Response to Request for Additional Information (RAI Regarding License Amendment Request (TSCR-135): Application for One-Time Technical Specification Change Regarding Core Spray Operability During Shutdown2012-06-27027 June 2012 Response to Request for Additional Information (RAI Regarding License Amendment Request (TSCR-135): Application for One-Time Technical Specification Change Regarding Core Spray Operability During Shutdown ML12107A1532012-04-13013 April 2012 NRR E-mail Capture - ME8251 - Duane Arnold - Preparations for Potential Bravo Diesel Generator LCO Extension TS 3.8.1 NG-12-0028, License Amendment Request (TSCR-132): Application for Technical Specification Change Regarding Battery Terminal and Charger Voltage and Amperage Section Affected: 3.8.42012-03-22022 March 2012 License Amendment Request (TSCR-132): Application for Technical Specification Change Regarding Battery Terminal and Charger Voltage and Amperage Section Affected: 3.8.4 ML1207402022012-03-21021 March 2012 Correction to Amendment No. 280 Regarding Adoption of Technical Specifications Task Force Traveler (TSTF-425) to Relocate Specific Surveillance Frequencies to a Licensee-Controlled Program NG-12-0054, Supplement to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program2012-02-0303 February 2012 Supplement to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program NG-11-0371, License Amendment Request (TSCR-129): Application for Technical Specification Change Regarding Alternative Testing of Safety/Relief Valves Sections Affected: 3.4.3, 3.5.1, and 3.6.1.52011-09-29029 September 2011 License Amendment Request (TSCR-129): Application for Technical Specification Change Regarding Alternative Testing of Safety/Relief Valves Sections Affected: 3.4.3, 3.5.1, and 3.6.1.5 NG-11-0299, Response to Request for Additional Information Related to an Amendment to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program2011-08-15015 August 2011 Response to Request for Additional Information Related to an Amendment to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program NG-11-0037, License Amendment Request (TSCR-120): Application for Technical Specification Change Regarding Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425, Rev. 3)2011-02-23023 February 2011 License Amendment Request (TSCR-120): Application for Technical Specification Change Regarding Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425, Rev. 3) 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 NG-09-0119, Request for Exemption from Certain Requirements of 10 CFR Part 50, Appendix J and Associated Changes to Technical Specifications for Main Steamline Isolation Valve Local Leakage Rate Testing (TSCR-096) Affected Technical Specification...2009-03-0404 March 2009 Request for Exemption from Certain Requirements of 10 CFR Part 50, Appendix J and Associated Changes to Technical Specifications for Main Steamline Isolation Valve Local Leakage Rate Testing (TSCR-096) Affected Technical Specification... ML0822601352008-09-0909 September 2008 Technical Specifications, Issuance of Amendment Regarding License Amendment Request to Remove the Emergency Diesel Generator Surveillance Requirement for Preplanned Preventive Maintenance and Testing ML0817805562008-06-24024 June 2008 Tech Spec Pages for Amendment 269 Adoption of Changes to TSTF-448, Revision 3, Control Room Habitability. NG-08-0312, Updated Technical Specification and Bases Pages Related to Technical Specification Change Request (TSCR-092): Consolidated Line Item Improvement; Adoption of Changes to Standard Specifications . .2008-05-0808 May 2008 Updated Technical Specification and Bases Pages Related to Technical Specification Change Request (TSCR-092): Consolidated Line Item Improvement; Adoption of Changes to Standard Specifications . . ML0808103592008-03-20020 March 2008 Technical Specifications, Amendment to Improve the Ranked Position Withdrawal Sequence Control Rod Insertion Process NG-07-0571, Application for Technical Specification Improvement to Adopt TSTF-476, Revision 1, Improved Banked Position Withdrawal Sequence (BPWS) Control Rod Insertion Process (NEDO-33091).2007-09-14014 September 2007 Application for Technical Specification Improvement to Adopt TSTF-476, Revision 1, Improved Banked Position Withdrawal Sequence (BPWS) Control Rod Insertion Process (NEDO-33091). NG-07-0493, Tscr: Consolidated Line Item Improvement, Adoption of Changes to STS Under TSTF-448, Revision 3 Regarding Control Room Envelopes Habitability2007-06-29029 June 2007 Tscr: Consolidated Line Item Improvement, Adoption of Changes to STS Under TSTF-448, Revision 3 Regarding Control Room Envelopes Habitability ML0717901682007-06-28028 June 2007 Tech Spec Pages for Amendment 265 Regarding Technical Specification Change Related to the Revised Rule for Combustible Gas Control ML0703804842007-02-0505 February 2007 Technical Specification, System Leakage and Hydrostatic Testing Operation ML0635405782006-12-14014 December 2006 Tech Spec Pages for Amendment 263 Regarding Inoperability of Snubbers ML0632500392006-11-15015 November 2006 Technical Specifications, Revises TS Table 3.3.6.1-1, Primary Containment Isolation Instrumentation, to Eliminate the Main Steamline Radiation Monitor Trip Function NG-06-0472, Technical Specification Change Request (TSCR-083): Adoption of TSTF-478, Rev. 0, 'Bwr Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Affected Tech Specs: Section 3.6.3.1 and 3.6.3.22006-07-17017 July 2006 Technical Specification Change Request (TSCR-083): Adoption of TSTF-478, Rev. 0, 'Bwr Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Affected Tech Specs: Section 3.6.3.1 and 3.6.3.2 NG-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 ML0627102722006-01-27027 January 2006 Technical Specifications, Transfer of License to FPL Energy Duane Arnold, LLC ML0603201602006-01-27027 January 2006 Appendix B - Additional Conditions Operating License No. DPR-49 ML0517404312005-06-24024 June 2005 (TS) - Correction to Amendment No. 258 Dated May 12, 2005 ML0517503432005-06-23023 June 2005 Technical Specifications, Revised Action for Scram Discharge Volume Vent and Drain Values ML0513301812005-05-12012 May 2005 Technical Specifications, Issuance of Amendment to Revise the Technical Specifications by Adopting TSTF Nos. 273, 284, and 299 ML0503401522005-01-31031 January 2005 Technical Specifications, Deletion Requirements for Submittal of Occupational Radiation and Monthly Operating Reports ML0501200762005-01-10010 January 2005 TS Pages for Amendment 255 Regarding Technical Specifications Adopt TSTF-359, Increased Flexibility in Mode Restraints NG-04-0689, Application for Technical Specification Improvement to Revise the Required Action within TS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process2004-10-29029 October 2004 Application for Technical Specification Improvement to Revise the Required Action within TS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process ML0324004962003-08-25025 August 2003 Technical Specification Page, Updating Reactor Coolant System Pressure and Temperature Limit Curves (TS Figure 3.4.9-1) and Extends Applicability to 32 Effective full-power Years ML0314100482003-05-16016 May 2003 License Amendment 251, License Page 4a, Pertaining to Reactor Building Crane and single-failure Proof NG-03-0304, Revision of Technical Specification Change Request (TSCR-059A): Update to Reactor Coolant System Pressure and Temperature Limit Curves.2003-05-0202 May 2003 Revision of Technical Specification Change Request (TSCR-059A): Update to Reactor Coolant System Pressure and Temperature Limit Curves. NG-03-0332, 2002 Annual Radioactive Materials Release Report2003-04-30030 April 2003 2002 Annual Radioactive Materials Release Report ML0308505872003-03-21021 March 2003 TS Page for Amendment No. 249 ML0229501072002-10-28028 October 2002 Correction to Issuance of Amendment No. 248, TAC MB4269 ML0227703442002-10-0202 October 2002 Tech Spec for Amendment No. 248, Organization 5.2 for Duane Arnold ML0227703312002-10-0101 October 2002 Technical Specifications, Extends On-line Battery Replacement Time ML0210800482002-05-30030 May 2002 License Amendment No. 246, Issuance of Amendment Missed Surveillance, Consolidated Line Item Improvement 2021-05-13
[Table view] |
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NEXTera M ENERGY~
~ DUANE ARNOLD June 27,2012 NG-12-0256 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 (RAil Regarding License Amendment Request (TSCR-135): Application for One-Time Technical Specification Change Regarding Core Spray Operability during Shutdown
Reference:
P. Wells (NextEra Energy Duane Arnold, LLC) to USNRC, "License Amendment Request (TSCR-135): Application for One-Time Technical Specification Change Regarding Core Spray Operability during Shutdown Section Affected: 3.3.5.1," NG-12-0167, dated May 1,2012 In the Referenced letter, NextEra Energy Duane Arnold, LLC (hereafter NextEra Energy Duane Arnold) requested, pursuant to 10 CFR 50.90, a one-time revision to the Technical Specifications (TS) for the Duane Arnold Energy Center (DAEC).
Subsequently, the NRC Staff has requested, via electronic mail, additional information regarding that application. Attachment 1 to this letter provides the responses to those requests for information.
As a result of the response to RAI #1, the original TS marked-up and clean, typed pages have been revised and the new pages are found in Attachment 2 and 3, respectively. This is considered an editorial change to the original application and the original evaluation of No Significant Hazards Consideration, per 10 CFR 50.92, submitted with the Referenced application, is not changed.
There are no new commitments or changes to any existing commitment being made in this letter.
If you have any questions or require additional information, please contact Steve Catron at 319-851-7234.
NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324
Document Control Desk June 27,2012 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on June 27,2012.
~jr Richard L. Ander~
Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC Attachments: 1) Responses to Requests for Additional Information
- 2) Revised Marked-up TS Page for TSCR-135
- 3) Revised Clean, Typed TS Page for TSCR-135 cc: M. Rasmusson (State of Iowa)
Attachment 1 to NG-12-0256 Page 1 of 6 REQUEST FOR ADDITIONAL INFORMATION (RAI)
REVISION TO ONE-TIME TS CHANGE REGARDING CS OPERABILITY DURING SHUTDOWN DUANE ARNOLD ENERGY CENTER (DAEC)
TAC # ME8572 By application dated May 1, 2012, NextEra Energy Duane Arnold LLC, requested changes to the Technical Specifications (TS) for Duane Arnold Energy Center (DAEC). The proposed change would revise the DAEC TS on a one-time basis by adding a footnote to TS Table 3.3.5.1-1, Function 1.d, Modes 4 and 5, specifying that Function 1.d is not required to be met during Refueling Outage 23 in Modes 4 and 5.
The NRC staff has identified the need for additional information to complete its review of the LAR. There are 2 Request for Additional Information Items (RAII) to which have been assigned tracking numbers to facilitate further discussion, if needed:
- 1. ME8572-RAII-STSB-Bucholz-001-2012-06-29 and
- 2. ME8572-RAII-SRXB-Razzaque-001-2012-06-29 These tracking numbers identify:
(1) the sources of RAII by Technical Branches (Technical Specifications (STSB) and Reactor Systems (SRXB) Branches; (2) the specific Reviewers, Kristy Bucholtz and Muhammad Razzaque, who requested the information along with a sequential number (in this case 001 for both) for unique identification; and (3) a request by date nominally set at June 29, 2012 (2012-06-29) subject to confirmation and based on the earlier decision to pursue an aggressive review schedule. Optional use of Bucholz-001 or Razzaque-001 in later correspondence or discussions would also uniquely identify items.
Common acronyms used in this RAI include (some acronyms are defined in close proximity to their use):
CFR = Code of Federal Regulations CST = Condensate Storage Tank ECCS = Emergency Core Cooling System LCO = Limited Condition of Operation RFO = Refueling Outage STSB = Technical Specifications Branch SRXB = Reactor Systems Branch SR = Surveillance Requirement TS = Technical Specifications
Attachment 1 to NG-12-0256 Page 2 of 6 ME8572-RAII-STSB-Bucholz-001-2012-06-29 In letter dated May 1, 2012, NextEra Energy Duane Arnold, LLC, (the licensee) proposed changes to the Technical Specifications (TS) for Duane Arnold Energy Center (DAEC). The proposed changes would revise the DAEC TS on a one-time basis by adding a footnote to TS Table 3.3.5.1-1, Function 1.d, Modes 4 and 5, specifying that Function 1.d is not required to be met during Refueling Outage 23 in Modes 4 and 5. DAEC TS Table 3.3.5.1-1 function 1.d currently states:
APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 1. Core Spray System
- d. Core Spray 1, 2, 3 1 per pump E SR 3.3.5.1.3 256.6 gpm Pump Discharge SR 3.3.5.1.8 and Flow - Low 4(a), 5(a) SR 3.3.5.1.9 2382.1 gpm (Bypass)
(a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS-Shutdown.
Specifically, the proposed changes, as shown below, would add footnote
- to Modes 4 and 5 in DAEC TS Table 3.3.5.1-1 for function 1.d.
APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 1. Core Spray System
- d. Core Spray 1, 2, 3 1 per pump E SR 3.3.5.1.3 256.6 gpm Pump Discharge SR 3.3.5.1.8 and Flow - Low 4(a)*, 5(a)* SR 3.3.5.1.9 2382.1 gpm (Bypass)
(a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS-Shutdown.
- This requirement is not required to be met during Refueling Outage (RFO) 23.
Basis for the Request The licensee stated in its application that the proposed TS change would revise the DAEC TS on a one-time basis by adding a note to TS Table 3.3.5.1-1, Function 1d, Modes 4 and 5, specifying that Function 1d is not required to be met during RFO 23 in Modes 4 and 5.
Attachment 1 to NG-12-0256 Page 3 of 6 Proposed footnote *, This requirement is not required to be met during Refueling Outage (RFO) 23, is not clear which requirement is referenced.
Request for Additional Information #1 Provide a footnote that states which requirement is affected, how the requirement is affected, when it is applicable, and the duration and/or time frame.
For example, Footnote *, The required channels per function for Function 1.d is 0 per pump during Refueling Outage 23 when in Modes 4 and 5.
Regulatory Analysis Basis 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit states:
Whenever a holder of a license, including a construction permit and operating license under this part, and an early site permit, combined license, and manufacturing license under part 52 of this chapter, desires to amend the license or permit, application for an amendment must be filed with the Commission, as specified in §§ 50.4 or 52.3 of this chapter, as applicable, fully describing the changes desired, and following as far as applicable, the form prescribed for original applications.
=== End ME8572-RAII-STSB-Bucholz-001-2012-06-29 ====
NextEra Energy Response:
The footnote has been revised to be clearer as requested. In addition, to improve visibility, the asterisk
- used to denote the footnote in the Table has been replaced with the letter e, and moved to the Required Channels per Function column, which is in keeping with the TS Writers Guide. The new footnote reads:
(e) During Refuel Outage (RFO) 23, the MODE 4 and 5 requirement for Function 1.d is revised to be zero (0) required channels per pump.
Attachments 2 and 3 to this letter contain the new marked-up TS page and the new clean, typed TS page, respectively.
Attachment 1 to NG-12-0256 Page 4 of 6 ME8572-RAII-SRXB-Razzaque-001-2012-06-29 In the Technical Specification (TS) for DAEC, Surveillance Requirement (SR) 3.5.2.2, (b) states
[A box was added for this RAI to contain the entire quote]:
NOTE-------------------------
Only one required CS subsystem may take credit for this option during OPDRVs. [Operations with the Potential for Draining the Reactor Vessel]
Condensate storage tank water level in one CST is 11 ft or 7 ft in both CSTs.
The staff understands that the main reason for the above noted TS requirement to allow only one Core Spray (CS) subsystem (out of two required low pressure ECCS subsystems) to take credit for drawing water from condensate storage tank (CST) is a consequence of the limited amount of water in the CST. In order to assure adequate supply of water, the other required ECCS subsystem pump is aligned to the Suppression Pool (SP). SP can be assumed to be an unlimited source of water because in case of a reactor pressure vessel (RPV) draindown, the drained water can be recycled back to RPV via SP (SP is designed to reject the decay heat to the ultimate heat sink). Therefore, the NRC staff believes that if both the CS pumps are to be aligned to CST (when SP is unavailable) with fuels still in the RPV, then a RPV draindown cannot be mitigated that lasts long enough to provide time to use all of available CST water.
Consequently, fuels in the RPV can become uncovered during such a postulated draindown scenario. In light of the above discussion, please provide the following additional information:
Justify how DAEC can prevent and mitigate such a draindown event during OPDRV, as postulated above, using two CS subsystems both of which are aligned to CST which has only limited amount of water and has no ultimate heat sink available. The justification should include reasonable assurance that DAEC is equipped to mitigate such a draindown event for the period when SP will be out of service for re-coating. Otherwise, the NRC staff believes that LCO 3.5.2 should be applicable in MODE 4 and MODE 5, except when the cavity level is 21 ft, 1 inch above the RPV flange, with the Spent Fuel Pool gates removed, as stated in the DAEC TS.
End ME8572-RAII-SRXB-Razzaque-001-2012-06-29 =
Attachment 1 to NG-12-0256 Page 5 of 6 NextEra Energy Response:
As noted by the Staff, the subject Note to SR 3.5.2.2 only allows one CS subsystem to be aligned to the CST during OPDRVs. NextEra Energy Duane Arnold considered this Note during the development of our application, but determined that the DAEC could continue to comply with the existing TS requirements of LCO 3.5.2 and consequently, NextEra Energy Duane Arnold did not request relief from this SR Note in our application. The requested TS change only affects the minimum flowpath (logic and valves) for the CS system. There are no requested changes in how the CSTs can be credited as a suction source for complying with LCO 3.5.2.
NextEra Energy Duane Arnold has reviewed the Actions contained in NRC Enforcement Guidance Memorandum (EGM) 11-003 regarding OPDRVs when Secondary Containment is not Operable in MODE 5 (ADAMS Accession Number ML11251A230). Accordingly, NextEra Energy Duane Arnold has scheduled all OPDRV activities in RFO23 to take place when either:
- 1. a. The Reactor Pressure Vessel (RPV) cavity is fully flooded up1, i.e., when LCO 3.5.2 is no longer required to be met and the SR 3.5.2.2 Note is no longer applicable, AND
- b. Secondary Containment is Operable.
OR
- 2. If the cavity is not flooded up (i.e., the LCO 3.5.2 Applicability is met and the Note to SR 3.5.2.2 applies):
- a. the minimum water level in the Suppression Pool is adequate, per SR 3.5.2.2, to support Residual Heat Removal (RHR) pump(s) for meeting LCO 3.5.2 (i.e., the Torus is not completely drained),
AND
- b. Secondary Containment is Operable.
To summarize, no credit will be taken during RFO23 for both CS pumps, with their suction piping aligned to the CST, for complying with LCO 3.5.2 during OPDRVs.
It should be noted that the draining of the Suppression Pool in MODES 4 and 5 does not result in a loss of decay heat removal to the ultimate heat sink, as the RHR System will be Operable for Shutdown Cooling mode, per TS LCOs, 3.4.8, 3.9.7, and 3.9.8.
1 RPV level greater than or equal to 21 feet, 1 inch above the RPV flange and the Spent Fuel Pool gates removed.
Attachment 1 to NG-12-0256 Page 6 of 6 NextEra Energy Duane Arnold will prevent challenges that could potentially become inadvertent draindown events by controlling the work activities, in accordance with the outage schedule. By controlling the outage activities during RFO23, in particular, those associated with OPDRVs, to when the RPV cavity is flooded or when the RHR pumps are available for complying with LCO 3.5.2, with the minimum required water level in the Torus, NextEra Energy Duane Arnold will assure that sufficient capability exists to mitigate potential draindown events, without over reliance on the CS subsystems being aligned to the CSTs.
In the event an unexpected draindown event does occur when the Torus is drained, there is a large inventory of makeup water available for mitigation. Because DAEC is a zero release plant for liquid radioactive effluents, none of the primary Reactor system water inventory is discarded; in particular, the approximately 400,000 gals of water removed from the Torus during the re-coat project. A total of approximately 1.1 Million gallons of water is stored in a combination of locations, at various times, during the RFO, such as the CSTs, RPV cavity, main condenser, Torus, and Radioactive Waste building. Thus, DAEC is not totally reliant on just the fixed amount of inventory in the CSTs for make-up capability during RFO23.
Attachment 2 to NG-12-0256 Revised Marked-up TS Page For TSCR-135 1 page to follow
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 1. Core Spray System
- a. Reactor Vessel Water 1,2,3, (b) B SR 3.3.5.1.1 > 38.3 inches 4
Level - Low Low Low (a) (a) SR 3.3.5.1.3 4 ,5 SR 3.3.5.1.8 SR 3.3.5.1.9
- b. Drywell Pressure - 1,2,3 (b) B SR 3.3.5.1.3 < 2.19 psig 4
High SR 3.3.5.1.8 SR 3.3.5.1.9
- c. Reactor Steam Dome 1,2,3 4 C SR 3.3.5.1.3 > 363.3 psig Pressure - Low SR 3.3.5.1.8 and < 485.1 psig (Injection Permissive) SR 3.3.5.1.9 (a) (a) 4 B SR 3.3.5.1.3 > 363.3 psig 4 ,5 (e)
SR 3.3.5.1.8 SR 3.3.5.1.9 and < 485.1 psig
- d. Core Spray Pump 1,2,3, 1 per E SR 3.3.5.1.3 > 256.6 gpm Discharge Flow - Low pump SR 3.3.5.1.8 and (Bypass) (a) (a) SR 3.3.5.1.9 < 2382.1 gpm 4 ,5
- e. Core Spray Pump Start 1,2,3, 1 per C SR 3.3.5.1.8 > 2.6 seconds Time Delay Relay (a) (a) pump SR 3.3.5.1.9 and < 6.8 seconds 4 ,5
- f. 4.16 kV Emergency Bus 1,2,3, 1 per F SR 3.3.5.1.5 < 3500 V Sequential Loading (a) (a) pump SR 3.3.5.1.6 Relay 4 ,5 SR 3.3.5.1.9
- 2. Low Pressure Coolant Injection (LPCI) System
- a. Reactor Vessel Water 1,2,3, 4 B SR 3.3.5.1.1 > 38.3 inches Level- Low Low Low (a) (a) SR 3.3.5.1.3 4 ,5 SR 3.3.5.1.8 SR 3.3.5.1.9
- b. Drywell Pressure - 1,2,3 4 B SR 3.3.5.1.3 < 2.19 psig High SR 3.3.5.1.8 SR 3.3.5.1.9 (continued)
(a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS-Shutdown.
(b) Also required to initiate the associated Diesel Generator (DG).
(e) During Refuel Outage (RFO) 23, the MODE 4 and 5 requirement for Function 1.d is revised to be zero (0) required channels per pump.
DAEC 3.3-41 TSCR-135
Attachment 3 to NG-12-0256 Revised Clean, Typed TS Page For TSCR-135 1 page to follow
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 1. Core Spray System
- a. Reactor Vessel Water 1,2,3, (b) B SR 3.3.5.1.1 > 38.3 inches 4
Level - Low Low Low (a) (a) SR 3.3.5.1.3 4 ,5 SR 3.3.5.1.8 SR 3.3.5.1.9
- b. Drywell Pressure - 1,2,3 (b) B SR 3.3.5.1.3 < 2.19 psig 4
High SR 3.3.5.1.8 SR 3.3.5.1.9
- c. Reactor Steam Dome 1,2,3 4 C SR 3.3.5.1.3 > 363.3 psig Pressure - Low SR 3.3.5.1.8 and < 485.1 psig (Injection Permissive) SR 3.3.5.1.9 (a) (a) 4 B SR 3.3.5.1.3 > 363.3 psig 4 ,5 SR 3.3.5.1.8 SR 3.3.5.1.9 and < 485.1 psig
- d. Core Spray Pump 1,2,3, 1 per E SR 3.3.5.1.3 > 256.6 gpm Discharge Flow - Low (a) (a) (e ) SR 3.3.5.1.8 and 4 ,5 pump (Bypass) SR 3.3.5.1.9 < 2382.1 gpm
- e. Core Spray Pump Start 1,2,3, 1 per C SR 3.3.5.1.8 > 2.6 seconds Time Delay Relay (a) (a) pump SR 3.3.5.1.9 and < 6.8 seconds 4 ,5
- f. 4.16 kV Emergency Bus 1,2,3, 1 per F SR 3.3.5.1.5 < 3500 V Sequential Loading (a) (a) pump SR 3.3.5.1.6 Relay 4 ,5 SR 3.3.5.1.9
- 2. Low Pressure Coolant Injection (LPCI) System
- a. Reactor Vessel Water 1,2,3, 4 B SR 3.3.5.1.1 > 38.3 inches Level- Low Low Low (a) (a) SR 3.3.5.1.3 4 ,5 SR 3.3.5.1.8 SR 3.3.5.1.9
- b. Drywell Pressure - 1,2,3 4 B SR 3.3.5.1.3 < 2.19 psig High SR 3.3.5.1.8 SR 3.3.5.1.9 (continued)
(a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS-Shutdown.
(b) Also required to initiate the associated Diesel Generator (DG).
(e) During Refuel Outage (RFO) 23, the MODE 4 and 5 requirement for Function 1.d is revised to be zero (0) required channels per pump.
DAEC 3.3-41 Amendment