Letter Sequence Request |
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EPID:L-2017-LLA-0288, License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating (Approved, Closed) |
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MONTHYEARNG-17-0127, License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating2017-09-0505 September 2017 License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating Project stage: Request ML18037B0032018-02-0606 February 2018 NRR E-mail Capture - Draft Request for Additional Information - Duane Arnold Energy Center (DAEC) - License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating - EPID L-2017-LLA-0288 Project stage: Draft RAI NG-18-0024, Response to Request for Additional Information Regarding License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, EGGS-Operating2018-03-0101 March 2018 Response to Request for Additional Information Regarding License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, EGGS-Operating Project stage: Response to RAI ML18179A1842018-08-16016 August 2018 Issuance of Amendment 306 to Revise Technical Specification 3.5.1, ECCS-Operating Project stage: Approval 2018-02-06
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Category:Letter type:NG
MONTHYEARNG-24-0004, 2023 Annual Radiological Environmental Operating Report2024-05-0808 May 2024 2023 Annual Radiological Environmental Operating Report NG-24-0003, Submittal of 2023 Annual Radioactive Material Release Report2024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Material Release Report NG-24-0001, 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update2024-03-0606 March 2024 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update NG-24-0002, 2023 Annual Exposure Report - Form 5s2024-03-0606 March 2024 2023 Annual Exposure Report - Form 5s 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 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-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s 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 2024-05-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML22033A0802022-02-0202 February 2022 Supplement to License Amendment Request (TSCR-188): Proposed Change to the Physical Security Plan for the Post-Shutdown and Permanently Defueled Condition 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 ML21167A1862021-06-0303 June 2021 License Amendment Request (TSCR-191): Proposed Change to the Physical Security Plan for the Isfsl Only Condition ML21105A7452021-04-0707 April 2021 Supplement to License Amendment Request (TSCR-188): Proposed Change to the Physical Security Plan for the Post-Shutdown and Permanently Defueled Condition 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-20-0022, License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements2020-05-15015 May 2020 License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements NG-20-0021, Supplement to License Amendment Request (TSCR-182): Proposed Changes to the Emergency Plan for Permanently Defueled Condition2020-03-11011 March 2020 Supplement to License Amendment Request (TSCR-182): Proposed Changes to the Emergency Plan for Permanently Defueled Condition NG-20-0017, License Amendment Request (TSCR-184) Non-SGI Document Retransmittal2020-02-24024 February 2020 License Amendment Request (TSCR-184) Non-SGI Document Retransmittal NG-20-0011, Supplement to License Amendment Request (TSCR-182): Proposed Changes to the Emergency Plan for Permanently Defueled Condition2020-02-21021 February 2020 Supplement to License Amendment Request (TSCR-182): Proposed Changes to the Emergency Plan for Permanently Defueled Condition ML20049A8222020-02-13013 February 2020 NextEra Energy Duane Arnold, LLC - License Amendment Request (TSCR-184): Proposed Change to the Physical Security Plan for the Post-Shutdown and Permanently Defueled Condition ML20044C8642020-02-0707 February 2020 License Amendment Request (TSCR-184): Proposed Change to the Physical Security Plan for the Post-Shutdown and Permanently Defueled Condition L-2019-161, License Amendment Request (TSCR-186): Removal of License Condition 2.C.(3), Fire Protection Program2019-09-25025 September 2019 License Amendment Request (TSCR-186): Removal of License Condition 2.C.(3), Fire Protection Program L-2019-157, Supplement to License Amendment Request (TSCR-183): Application to Revise Technical Specifications for the Permanently Defueled Condition2019-09-12012 September 2019 Supplement to License Amendment Request (TSCR-183): Application to Revise Technical Specifications for the Permanently Defueled Condition L-2019-105, License Amendment Request (TSCR-183): Application to Revise Operating License and Technical Specifications for Permanently Defueled Condition2019-06-20020 June 2019 License Amendment Request (TSCR-183): Application to Revise Operating License and Technical Specifications for Permanently Defueled Condition L-2019-050, License Amendment Request (TSCR-181): Application to Align Technical Specification Staffing and Administrative Requirements for Permanently Defueled Condition2019-04-19019 April 2019 License Amendment Request (TSCR-181): Application to Align Technical Specification Staffing and Administrative Requirements for Permanently Defueled Condition ML19101A2622019-04-0909 April 2019 License Amendment Request (TSCR-182): Proposed Changes to the Emergency Plan for Permanently Defueled Condition NG-17-0236, License Amendment Request (TSCR-179) Application to Add Technical Specification 3.2.3. Linear Heat Generation Rate.2017-12-19019 December 2017 License Amendment Request (TSCR-179) Application to Add Technical Specification 3.2.3. Linear Heat Generation Rate. NG-17-0235, Attachment 1: Duane Arnold Energy Center, License Amendment Request TSCR-166, Redline Markup of NEI 99-01, Revision 6. Part 1 of 22017-12-15015 December 2017 Attachment 1: Duane Arnold Energy Center, License Amendment Request TSCR-166, Redline Markup of NEI 99-01, Revision 6. Part 1 of 2 NG-17-0235, Duane Arnold Energy Center, License Amendment Request TSCR-166, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2017-12-15015 December 2017 Duane Arnold Energy Center, License Amendment Request TSCR-166, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. NG-17-0235, Attachment 2: Duane Arnold Energy Center, License Amendment Request TSCR-166, Clean Copy of the Proposed DAEC EAL Scheme2017-12-15015 December 2017 Attachment 2: Duane Arnold Energy Center, License Amendment Request TSCR-166, Clean Copy of the Proposed DAEC EAL Scheme NG-17-0235, Attachment 1: Duane Arnold Energy Center, License Amendment Request TSCR-166, Redline Markup of NEI 99-01, Revision 6. Part 2 of 22017-12-15015 December 2017 Attachment 1: Duane Arnold Energy Center, License Amendment Request TSCR-166, Redline Markup of NEI 99-01, Revision 6. Part 2 of 2 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 ML17363A0692017-12-15015 December 2017 Duane Arnold Energy Center, License Amendment Request TSCR-166, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. ML17363A0712017-12-15015 December 2017 Attachment 1: Duane Arnold Energy Center, License Amendment Request TSCR-166, Redline Markup of NEI 99-01, Revision 6. Part 1 of 2 ML17363A0722017-12-15015 December 2017 Attachment 1: Duane Arnold Energy Center, License Amendment Request TSCR-166, Redline Markup of NEI 99-01, Revision 6. Part 2 of 2 ML17363A0742017-12-15015 December 2017 Attachment 2: Duane Arnold Energy Center, License Amendment Request TSCR-166, Clean Copy of the Proposed DAEC EAL Scheme NG-17-0127, License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating2017-09-0505 September 2017 License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating NG-17-0169, License Amendment Request TSCR-175, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2017-08-31031 August 2017 License Amendment Request TSCR-175, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors NG-17-0093, License Amendment Request (TSCR-168), Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-06-0909 June 2017 License Amendment Request (TSCR-168), Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control NG-17-0084, License Amendment Request (TSCR-164), Revision to Technical Specification 3.1.2, Reactivity Anomalies2017-04-20020 April 2017 License Amendment Request (TSCR-164), Revision to Technical Specification 3.1.2, Reactivity Anomalies NG-17-0037, Duane Arnold Energy Center - Submittal of License Amendment Request (TSCR-165) for Revision to Emergency Planning Zone in the Duane Arnold Energy Center Emergency Plan2017-03-31031 March 2017 Duane Arnold Energy Center - Submittal of License Amendment Request (TSCR-165) for Revision to Emergency Planning Zone in the Duane Arnold Energy Center Emergency Plan NG-17-0037, Duane Arnold Energy Center - Evaluation of Proposed Amendment for License Amendment Request (TSCR-165) for Revision to Emergency Planning Zone in the Duane Arnold Energy Center Emergency Plan2017-03-31031 March 2017 Duane Arnold Energy Center - Evaluation of Proposed Amendment for License Amendment Request (TSCR-165) for Revision to Emergency Planning Zone in the Duane Arnold Energy Center Emergency Plan ML17102B1842017-03-31031 March 2017 Duane Arnold Energy Center - Evaluation of Proposed Amendment for License Amendment Request (TSCR-165) for Revision to Emergency Planning Zone in the Duane Arnold Energy Center Emergency Plan ML17102B1832017-03-31031 March 2017 Duane Arnold Energy Center - Submittal of License Amendment Request (TSCR-165) for Revision to Emergency Planning Zone in the Duane Arnold Energy Center Emergency Plan NG-17-0069, License Amendment Request (TSCR-169), Revision to Technical Specification Table 3.3.2.1-1, Control Rod Block Instrumentation2017-03-24024 March 2017 License Amendment Request (TSCR-169), Revision to Technical Specification Table 3.3.2.1-1, Control Rod Block Instrumentation NG-17-0037, Kld TR-910, Duane Arnold Energy Center Development of Evacuation Time Estimates for Revised EPZ Boundary (in Support of License Amendment Request (TSCR-165))2017-03-0909 March 2017 Kld TR-910, Duane Arnold Energy Center Development of Evacuation Time Estimates for Revised EPZ Boundary (in Support of License Amendment Request (TSCR-165)) NG-16-0102, License Amendment Request (TSCR-161) to Revise Technical Specifications 2.1.1.2 Safety Limit Minimum Critical Power Ratio, and to Remove an Outdated Historical Footnote from Table 3.3.5.1-12016-05-18018 May 2016 License Amendment Request (TSCR-161) to Revise Technical Specifications 2.1.1.2 Safety Limit Minimum Critical Power Ratio, and to Remove an Outdated Historical Footnote from Table 3.3.5.1-1 ML16145A1832016-04-30030 April 2016 Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Cycle 26 NG-16-0052, License Amendment Request (TSCR-159) to Revise Technical Specifications Fuel Storage Requirements2016-03-15015 March 2016 License Amendment Request (TSCR-159) to Revise Technical Specifications Fuel Storage Requirements NG-15-0284, License Amendment Request (TSCR-1 30) for Amendment to Technical Specifications Section 5.5.6 for the Inservice Testing Program2015-10-14014 October 2015 License Amendment Request (TSCR-1 30) for Amendment to Technical Specifications Section 5.5.6 for the Inservice Testing Program NG-15-0234, License Amendment Request (TSCR-143) to Extend Containment Leakage Test Frequency2015-08-18018 August 2015 License Amendment Request (TSCR-143) to Extend Containment Leakage Test Frequency NG-15-0048, License Amendment Request (TSCR-153) to Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits2015-08-0606 August 2015 License Amendment Request (TSCR-153) to Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits NG-15-0230, License Amendment Request (TSCR-1 54) to Correct Examples in Technical Specifications Section 1.4, Frequency.2015-07-24024 July 2015 License Amendment Request (TSCR-1 54) to Correct Examples in Technical Specifications Section 1.4, Frequency. NG-14-0291, License Amendment Request (TSCR-1 51) for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2015-01-26026 January 2015 License Amendment Request (TSCR-1 51) for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control NG-14-0150, License Amendment Request (TSCR-147): Application to Revise Cyber Security Plan Milestone 8 Completion Date2014-08-28028 August 2014 License Amendment Request (TSCR-147): Application to Revise Cyber Security Plan Milestone 8 Completion Date 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-13-0110, License Amendment Request (TSCR-140): Application to Revise Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs, Section Affected: 1.12013-03-14014 March 2013 License Amendment Request (TSCR-140): Application to Revise Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs, Section Affected: 1.1 NG-12-0483, License Amendment Request (TSCR-142): Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hrs Per Month, Using Consolidated Line Item Improvement Process2012-12-21021 December 2012 License Amendment Request (TSCR-142): Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hrs Per Month, Using Consolidated Line Item Improvement Process 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 2022-02-02
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NEXTera"'
E N ERGY~
DUANE ARNOLD September 5, 2017 NG-17-0127 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Duane Arnold Energy Center Docket No. 50-331 License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, EGGS-Operating Pursuant to 10 CFR 50.90, NextEra Energy Duane Arnold, LLC (NextEra) hereby requests an amendment to the Duane Arnold Energy Center (DAEC) Technical Specifications (TS). The proposed amendment would revise the DAEC TS by modifying an existing Surveillance Requirement (SR) regarding the Automatic Depressurization System (ADS) nitrogen supply: As discussed in the Enclosure, the proposed change does not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the change.
The Enclosure to this letter provides NextEra's evaluation of the proposed change.
Attachment 1 to the Enclosure provides a markup of the TS showing the proposed changes, Attachment 2 provides the clean-typed TS pages and Attachment 3 provides the proposed TS Bases changes. The changes to the TS Bases are provided for information only and will be incorporated in accordance with the TS Bases Control Program upon implementation of the approved amendment.
NextEra requests approval of the proposed license amendment by September 1, 2018.
Once approved, the amendment shall be implemented within 90 days.
This letter contains no new or revised regulatory commitments.
In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being provided to the designated State of Iowa official.
If you have any questions or require additional information, please contact Michael Davis, Licensing Manager, at 319-851-7032.
NextEra Energy Duane Arnold, LLC , 3277 DAEC Road , Palo, IA 52324
Document Control Desk NG-17-0127 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on September 5, 2017.
&,~
Dean Curtland Site Director, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC
Enclosure:
Evaluation of the Proposed Change cc: Regional Administrator, USNRC, Region Ill, Project Manager, USNRC, Duane Arnold Energy Center Resident Inspector, USNRC, Duane Arnold Energy Center A. Leek (State of Iowa)
ENCLOSURE to NG-17-0127 NEXTERA ENERGY DUANE ARNOLD, LLC DUANE ARNOLD ENERGY CENTER License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating EVALUATION OF PROPOSED CHANGE 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION 2.1 System Design and Operation 2.2 Current TS Requirements 2.3 Reason for the Proposed Change 2.4 Description of the Proposed Change
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA 4.2 NO SIGNIFICANT HAZARDS CONSIDERATION
4.3 CONCLUSION
S
5.0 ENVIRONMENTAL CONSIDERATION
S - Proposed Technical Specification Changes (Mark-Up) - Revised Technical Specification Pages - Proposed Technical Specification Bases Changes (Mark-Up)
Page 1 of 7
1.0
SUMMARY
DESCRIPTION NextEra Energy Duane Arnold, LLC (NextEra) hereby requests an amendment to the Duane Arnold Energy Center (DAEC) Technical Specifications {TS) to modify TS 3.5.1, "ECCS-Operating." The proposed change would decrease the nitrogen supply requirement for the Automatic Depressurization System (ADS) in Surveillance Requirement (SR) 3.5.1.3 from 100 days to 30 days.
2.0 DETAILED DESCRIPTION 2.1 System Design and Operation The purpose of the Automatic Depressurization System (ADS) is to provide an automatic means of reducing reactor pressure for events such as pipe breaks or reactor loss of water level transients when the High Pressure Coolant Injection (HPCI) System is unable to maintain reactor water level. The pressure reduction enables low pressure injection systems such as Low Pressure Coolant Injection (LPCI) mode of the Residual Heat Removal (RHR) System and Core Spray (CS) to inject additional makeup water into the vessel to restore or maintain water level preventing overheating of the fuel cladding.
The ADS utilizes four of the six safety/relief valves (SRVs) provided in the Nuclear Boiler System to accomplish reactor vessel depressurization. The four ADS valves open in response to reactor low level signals, which indicate that a loss of coolant accident (LOCA) has occurred.
The presence of an ADS initiation signal indicates that the HPCI system is unable to maintain reactor vessel water level and additional injection sources are required. The ADS will then act to reduce reactor vessel pressure to the point where the low pressure injection sources, such as LPCI and CS, are capable of reactor vessel injection.
The ADS SRVs are equipped with nitrogen accumulators and check valves to store pneumatic energy for relief valve operation. Each ADS SRV accumulator has a volume of 200 gallons and is equipped with an inlet check valve at the boundary between the safety-grade accumulator system and the non-safety related drywell nitrogen supply system. The inlet check valves serve to minimize the loss of nitrogen from the ADS accumulators in the event that the normal drywell nitrogen supply system should fail.
The normal pneumatic supply to the ADS SRVs is from the drywell nitrogen supply system. The drywell nitrogen supply system is a recirculation system maintained through a pneumatic supply system compressor, which takes a suction from the drywell. The drywell nitrogen supply system also maintains pressure in the ADS SRV accumulators.
When the drywell nitrogen system accumulator pressure drops to the setpoint, the compressor is started and nitrogen is supplied to the drywell nitrogen system accumulator. In the automatic operating mode, the compressor starts at a nitrogen accumulator pressure of 95 psig and stops when the system accumulator reaches 105 psig. The compressor can be manually operated.
The nitrogen compressor is capable of being powered from onsite. In the event of a loss of offsite power, manual switchover provides the nitrogen compressor with onsite emergency diesel power.
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2.2 Current Technical Specifications Requirements The current DAEC TS contains a SR to verify that a 100-day nitrogen supply exists for each ADS accumulator in Mode 1 and in Modes 2 and 3 when reactor steam dome pressure is> 100 psig. This SR can be met by either: 1) verifying that the drywell nitrogen header supply pressure is ;::: 90 psig, or 2) when drywell nitrogen header supply pressure is < 90 psig, using the actual accumulator check valve leakage rates obtained from the most-recent tests to determine, analytically, that a 100 day supply of nitrogen exists for each accumulator. The results of this analysis can also be used to determine when the 100 day supply of nitrogen will no longer exist for individual ADS accumulators, and when each ADS valve would subsequently be required to be declared inoperable, assuming the drywell nitrogen supply pressure is not restored to ;::: 90 psig.
The current TS action for two or more ADS valves inoperable during Modes of applicability requires entering Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reducing reactor steam dome pressure to ::;; 100 psig in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
2.3 Reason for the Proposed Change Industry operating experience revealed that vendor information used to calculate ADS accumulator sizing was incorrect. The volume of air required to stroke the operators was actually 40 cubic inches instead of 15 cubic inches. Since discovery, the ADS accumulators have remained operable; however the 100-day nitrogen supply is close to being challenged.
Review of the DAEC accident analyses has shown that the worst-case DAEC accident scenario will require the use of ADS for 3 days post-accident. Reducing the duration of time from 100 days to 30 days still provides ample conservativism for the DAEC accident analyses and allows for an increase in accumulator margin.
2.4 Description of the Proposed Change SURVEILLANCE FREQUENCY SR 3.5.1.3 Verify a 4-00 30-day supply of nitrogen exists for each In accordance ADS accumulator. with the Surveillance Frequency Control Program The proposed change is supported by changes to the TS Bases. The regulation at Title 10 of the Code of Federal Regulations (10 CFR), Part 50.36, states, "A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications."
Changes to the TS Bases will be made in accordance with the Technical Specifications Bases Control Program following approval of the requested amendment. The proposed TS Bases changes are consistent with the proposed TS change and provide the purpose for each requirement in the specification consistent with the Commission's Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 2, 1993 (58 FR 39132). Therefore, the Bases changes are provided for information and approval of the Bases is not requested.
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3.0 TECHNICAL EVALUATION
The primary purpose of the long-term ADS is to keep the reactor pressure low enough so low-pressure emergency core cooling systems (ECCS) can be used to keep the core cooled.
The current DAEC ECCS-LOCA analyses have been reviewed. The Main Steam Line Break Outside Containment (MSLO) is the limiting scenario regarding SRV actuations. Eleven (11)
SRV actuations are estimated for this event, including the ADS actuations, and the maximum required time of ADS availability to meet any LOCA event is found to be no longer than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
While a 100-day ADS nitrogen supply is not specifically credited in the following analyses, Containment, Fire Protection (NFPA 805), Station Blackout (SBO) and Anticipated Transient Without Scram (ATWS) analyses have also been reviewed. The review concluded that the reactor would be depressurized by HPCl/RCIC and/or ADS operation within 3 days following any postulated accident or event that would create a hostile environment in the drywell. Once initial depressurization is completed, long term core cooling can be assured without ADS either by operation of the shutdown cooling mode of RHR or by utilizing low pressure ECCS.
Therefore, the TS SR to verify a 100-day supply of nitrogen is overly conservative and can be reduced to 30 days while maintaining more than sufficient margin.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements The following NRC requirements are applicable to the proposed change.
The regulations at Title 10 of the Code of Federal Regulations (10 CFR) Part 50.36 Technical specifications," establish the requirements related to the content of the TS. Section 50.36(c)(3) states:
Surveillance requirements. Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
The regulatory requirements in 10 CFR 50.36 are not specific regarding the actions to be followed when TS are not met other than a plant shut down. The proposed change to the TS Surveillance Requirement will continue to maintain adequate margin such that safety limits will not be challenged and limiting conditions for operation will be met. The proposed change does not impact quality of the system. Therefore, the proposed change is consistent with the requirements of 10 CFR 50.36.
10 CFR 50.46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, requires an ECCS system that meets the criteria in 10 CFR 50.46(b) for cooling performance following a LOCA. The DAEC UFSAR Chapter 3 contains an evaluation of the design basis of the DAEC as measured against the Atomic Energy Commission (AEC) General Design Criteria (GDC) for nuclear power plants, Appendix A, of 10 CFR 50 effective May 21, 1971, and subsequently amended July 7, 1971. Criteria 35, 36 and 37 state:
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Criterion 35-Emergency core cooling. A system to provide abundant emergency core cooling shall be provided. The system safety function shall be to transfer heat from the reactor core following any loss of reactor coolant at a rate such that (1) fuel and clad damage that could interfere with continued effective core cooling is prevented and (2) clad metal-water reaction is limited to negligible amounts.
- Suitable redundancy in components and features, and suitable interconnections, leak detection, isolation, and containment capabilities shall be provided to assure that for onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be accomplished, assuming a single failure.
Criterion 36-/nspection of emergency core cooling system. The emergency core cooling system shall be designed to permit appropriate periodic inspection of important components, such as spray rings in the reactor pressure vessel, water injection nozzles, and piping, to assure the integrity and capability of the system.
Criterion 37-Testing of emergency core cooling system. The emergency core cooling system shall be designed to permit appropriate periodic pressure and functional testing to assure ( 1) the structural and leaktight integrity of its components, (2) the operability and performance of the active components of the system, and (3) the operability of the system as a whole and, under conditions as close to design as practical, the performance of the full operational sequence that brings the system into operation, including operation of applicable portions of the protection system, the transfer between normal and emergency power sources, and the operation of the associated cooling water system.
The proposed change has no effect on the current design of the ADS since it makes no physical changes to the system. Therefore, the proposed change has no effect on the application of these criteria.
NUREG-0737 Item ll.K.3.28 "Verify Qualifications of Accumulators on Automatic Depressurization System Valves" states:
Position. Safety analysis reports claim that air or nitrogen accumulators for the automatic depressurization system (ADS) valves are provided with sufficient capacity to cycle the valves open five times at design pressures. GE has also stated that the emergency core cooling (ECC) systems are designed to withstand a hostile environment and still perform their function for 100 days following an accident. Licensee should verify that the accumulators on the ADS valves meet these requirements, even considering normal leakage. If this cannot be demonstrated, the licensee must show that the accumulator design is still acceptable.
The Technical Evaluation above shows that the accumulator design is still acceptable.
Therefore, the NUREG-0737 Item 11.K.3.28 position is still met.
The proposed change does not affect compliance with these regulations or guidance and will ensure that the functional capabilities or performance levels of equipment required for safe operation are met.
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4.2 No Significant Hazards Consideration Analysis The DAEC Technical Specifications {TS) currently require verifying a 100-day supply of nitrogen exists for each ADS accumulator. The proposed amendment will change the requirement to verifying a 30-day supply of nitrogen exists for each ADS accumulator.
NextEra has evaluated whether or not a significant hazards consideration is involved with the proposed amendment using the criteria in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change modifies a SR for verification of the nitrogen supply for the ADS accumulators. Accidents are initiated by the malfunction of plant equipment, or the catastrophic failure of plant structures, systems or components. The performance of this surveillance is not a precursor to any accident previously evaluated and does not change the manner in which the ADS operates. Technical evaluation of the change concluded that a 30-day nitrogen supply is more than adequate to ensure that the reactor is depressurized, so the consequences of an accident remain unchanged.
Therefore, the proposed change does not involve a significant increase in the probability or consequence of a previously evaluated accident
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change does not involve physical alterations to the plant. No new or different type of equipment will be installed, and there are no physical modifications required to existing installed equipment associated with the proposed change. The proposed change does not create any failure mechanism, malfunction or accident initiator not already considered in the design and licensing basis.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No Although the proposed change will decrease the required supply of nitrogen for the ADS accumulators from 100 days to 30 days, the assessment above has shown that the reactor would be depressurized within 3 days following any postulated accident or event that would create a hostile environment in the drywell. Once initial depressurization is completed, long term core cooling can be assured without ADS. Therefore, the proposed change will not involve a significant reduction in a margin of safety.
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Based on the above, NextEra concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92{c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.3 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
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ATTACHMENT 1 Proposed Technical Specification Changes (Mark-Up) 1 page follows
ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5 .1.2 -------------------------------NOTE-------------------------------------
The low pressure coolant injection (LPCI) system may be considered OPERABLE during alignment and operation for decay heat removal in MODE 3, if capable of being manually realigned and not otherwise inoperable.
NOTE-------------------------------------
Not required to be met for system vent flow paths opened under administrative control.
Verify each ECCS injection/spray subsystem power In accordance operated and automatic valve in the flow path, that is not with the locked , sealed, or otherwise secured in position, is in the Surveillance correct position. Frequency Control Program SR 3.5.1.3 Verify a 40030-day supply of nitrogen exists for each In accordance ADS accumulator. with the Surveillance Frequency Control Program SR 3.5.1.4 Verify the following ECCS pumps develop the specified In accordance flow rate against a system head corresponding to the with the specified reactor pressure. INSERVICE TESTING PROGRAM SYSTEM HEAD NO. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray 2: 2718 gpm 1 2: 113 psig LPCI 2: 4320 gpm 1 2: 20 psig (continued)
DAEC 3.5-5 Amendment JQG
ATTACHMENT 2 Revised Technical Specification Pages 1 page follows
ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.2 -------------------------------NOTE-------------------------------------
The low pressure coolant injection (LPCI) system may be considered OPERABLE during alignment and operation for decay heat removal in MODE 3, if capable of being manually realigned and not otherwise inoperable.
NOTE-------------------------------------
Not required to be met for system vent flow paths opened under administrative control.
Verify each ECCS injection/spray subsystem power In accordance operated and automatic valve in the flow path, that is not with the locked, sealed, or otherwise secured in position, is in the Surveillance correct position. Frequency Control Program SR 3.5.1.3 Verify a 30-day supply of nitrogen exists for each ADS In accordance accumulator. with the Surveillance Frequency Control Program SR 3.5.1.4 Verify the following ECCS pumps develop the specified In accordance flow rate against a system head corresponding to the with the specified reactor pressure. INSERVICE TESTING PROGRAM SYSTEM HEAD NO. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray ~ 2718 gpm 1 ~ 113 psig LPCI ~ 4320 gpm 1 ~ 20 psig (continued)
DAEC 3.5-5 Amendment
ATTACHMENT 3 Proposed Technical Specification Bases Changes (Mark-Up) 1 page follows
BASES SURVEILLANCE SR 3.5.1.3 REQUIREMENTS (continued)
Verification that a 4-0030-day supply of nitrogen exists for each ADS accumulator ensures adequate nitrogen pressure for reliable ADS operation. The accumulator on each ADS valve provides pneumatic pressure for valve actuation. The design pneumatic supply pressure requirements for the accumulator are such that following a failure of the pneumatic supply to the accumulator, each ADS valve can be actuated at least 5 times up to 4-0030 days following a LOCA (Reference 4). This SR can be met by either: 1) verifying that the drywell nitrogen header supply pressure is 2 90 psig, or 2) when drywell nitrogen header supply pressure is< 90 psig, using the actual accumulator check valve leakage rates obtained from the most-recent tests to determine, analytically, that a 4-0030-day supply of nitrogen exists for each accumulator. The results of this analysis can also be used to determine when the 4-0030-day supply of nitrogen will no longer exist for individual ADS accumulators, and when each ADS valve would subsequently be required to be declared inoperable, assuming the drywell nitrogen supply pressure is not restored to 2 90 psig. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Frequency takes into consideration administrative controls over operation of the nitrogen system and alarms for low nitrogen pressure.
SR 3.5.1.4. SR 3.5.1.5. and SR 3.5.1.6 The performance requirements of the low pressure ECCS pumps are determined through application of the 10 CFR 50, Appendix K criteria (Ref. 8). This periodic Surveillance is performed (in accordance with the ASME Code requirements for the ECCS pumps) to verify that the ECCS pumps will develop the flow rates required by the respective analyses. The low pressure ECCS pump flow rates ensure that adequate core cooling is provided to satisfy the acceptance criteria of Reference 10. The pump flow rates are verified against a system head equivalent to the RPV pressure expected during a LOCA. The total system pump outlet pressure is adequate to overcome the elevation head pressure between the pump suction and the vessel discharge, the piping friction losses, and RPV pressure present during a LOCA. These values may be established during preoperational testing or by analysis.
(continued)
DAEC B 3.5-15 Amendment