Quality Assurance Program Requirements (Design and Construction) (Task Rs 002-5)
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RIS 2018-05, Supplier Oversight Issues Identified During Recent NRC Vendor Inspections
RA-17-0025, Transmittal of the Duke Energy Corporation Topical Report (Duke-QAPD-001-A), Amendment 42
L-2017-122, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 21 Annual Submittal
CNL-16-204, Bellefonte, Units 1 and 2, Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 33
NL-16-2486, Submittal of Quality Assurance Topical Report, Version 15.0
NOC-AE-16003409, Submittal of Operations Quality Assurance Plan Change QA-084
NL-16-0998, Vogtle Electric Generating Plant - Quality Assurance Topical Report
L-2016-129, NextEra Energy Quality Assurance Topical Report (QATR FPL-1) Revision 19 Annual Submittal
NOC-AE-16003342, Submittal of Operations Quality Assurance Plan Change QA-083
NOC-AE-16003326, Submittal of Revised Operations Quality Assurance Plan, Revision 22
RIS 2000-18, Guidance on Managing Quality Assurance Records in Electronic Media
RIS 2011-14, Metal Fatigue Analysis Performed by Computer Software
Information Notice 2011-01, Commercial Grade Dedication Issues Identified During NRC Inspections
RA-18-008, Summary of Changes to Quality Assurance Topical Report, NO-AA-10
CNL-17-154, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 34
L-2015-184, Units 1 and 2, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 17
CNL-14-162, Bellefonte, Units 1 and 2, Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 & 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A
L-2014-201, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 14
NOC-AE-14003071, Submittal of Revised Operations Quality Assurance Plan
CNL-13-134, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A
L-2013-208, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 13
NOC-AE-13003012, Submittal of Operations Quality Assurance Plan Change QA-079
NOC-AE-12002903, Response to Requests for Additional Information - Operations Quality Assurance Plan (Oqap), Revision 20
NOC-AE-12002887, Submittal of Operations Quality Assurance Plan Change QA-075
NOC-AE-12002863, Submittal of Operations Quality Assurance Plan Change QA-074
NOC-AE-12002781, Submittal of Revised Operations Quality Assurance Plan
NOC-AE-11002768, Submittal of Operations Quality Assurance Plan Change QA-073
L-2011-243, Submittal of Quality Assurance Topical Report (QATR FPL-1), Revision 9
GNRO-2011/00039, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System
NOC-AE-11002637, Submittal of Operations Quality Assurance Plan Change QA-072
BVY 18-012, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3), 10CFR71.106 and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G
NL-18-0854, Quality Assurance Topical Report Submittal
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
L-2016-198, Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 7.5, Safety-Related Display Instrumentation
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NOC-AE-10002614, Submittal of Operations Quality Assurance Plan Change QA-071
L-2010-138, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 7
NOC-AE-09002460, Submittal of Operations Quality Assurance Plan Change QA-069
L-2009-134, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 4
NOC-AE-09002418, Submittal of Operations Quality Assurance Plan Change QA-068
NOC-AE-08002314, Submittal of Operations Quality Assurance Plan Change QA-067
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RA-08-006, Submittal of Exelon Generation Company, LLC and Amergen Energy Company, LLC Quality Assurance Topical Report, NO-AA-10, Revision 80
NOC-AE-08002256, Submittal of Revised Operations Quality Assurance Plan
RAIO-0218-58628, LLC - Response to NRC Request for Additional Information No. 296 (Erai No. 9231) on the NuScale Design Certification Application
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
CY-02-010, Proposed Technical Specification Change Response to Request for Additional Information
L-2007-110, Topical Quality Assurance Report (Fpltqar 1-76A)
NOC-AE-07002171, Submittal of Operations Quality Assurance Plan Change QA-066
NOC-AE-07002157, Submittal of Operations Quality Assurance Plan Change QA-065
NOC-AE-07002138, Submittal of Rev. 17 to Operations Quality Assurance Plan Change QA-064
L-2006-208, Plants - Response to Request for Additional Information Regarding Common Quality Assurance Topical Report
NOC-AE-06002050, Submittal of Operations Quality Assurance Plan Change QA-061
L-2006-164, Topical Quality Assurance Report (Fpltqar 1-76A)
NOC-AE-06002030, Submittal of Operation Quality Assurance Plan Change QA-060
NOC-AE-06001961, Submittal of Revised Operations Quality Assurance Plan
RBG-46478, Revised License Amendment Request (LAR) 2004-26, Use of the Fuel Building Cask Handling Crane for Dry Spent Fuel Cask Loading Operations Dated March 8, 2005
NRC-2009-0309, Federal Register Notice of Issuance of Regulatory Guide 1.200 Rev 2, License Renewal Interim Staff Guidance LR-ISG-2008-01: Staff Guidance Regarding the Station Blackout Rule (10 CFR 50.63) Associated with License Renewal Applications
RA-19-0115, Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 44
RA-18-0004, Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 43
NRC Generic Letter 88-18, Plant Record Storage on Optical Disks
CNL-19-043, Bellefont Nuclear Plant, Units 1 & 2; Browns Ferry Nuclear Plan, Units 1, 2 & 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, R
RAIO-0418-59775, LLC - Response to NRC Request for Additional Information No. 384 (Erai No. 9391) on the NuScale Design Certification Application
L-2019-134, Units 1 and 2 - Quality Assurance Topical Report, Revision 22, Annual Submittal
NL-19-0710, Quality Assurance Topical Report Submittal
NOC-AE-18003540, Submittal of Revised Operations Quality Assurance Plan
NOC-AE-05001908, Submittal of Operations Quality Assurance Plan Change OA-058
RS-19-075, Request for Approval of Change to Quality Assurance Topical Report
CNL-20-026, Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)
L-2018-123, Quality Assurance Program Description for 10 CFR Part 52 Licenses FPL-2 Revision 4
CNL-18-076, Update to Site Safety Analysis Report Section 17.5, Quality Assurance, in Support of Early Site Permit Application for Clinch River Nuclear Site
CNL-18-049, Clinch River Nuclear Site, Response to NRC Request for Additional Information 12 in Support of Early Site Permit Application for Clinch River Nuclear Site
ND-18-0295, Nuclear Development Quality Assurance Manual Version 18.0
ND-12-0606, Report of Changes to Quality Assurance Program Description
ND-20-0005, Enclosure - Nuclear Development Quality Assurance Manual Version 20.0
NLS2004138, Quality Assurance Program Revision 15
L-HU-04-039, Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 2004
RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)
NOC-AE-04001686, Submittal of Operations Quality Assurance Plan Change QA-056
NOC-AE-04001665, Submittal of Revised Operations Quality Assurance Plan
NOC-AE-03001553, Submittal of Operations Quality Assurance Plan Change QA-055
1CAN040302, License Amendment Request to Modify the Fuel Assembly Enrichment, the Spent Fuel Pool (SFP) Boron Concentration TS 3. 7.14, the Loading Restrictions in the SFP in TS 3,7,15m and to Modify the Fuel Storage Design Features in TS 4.3
2CAN010304, Arkansas, Unit 2, License Amendment Request to Change Spent Fuel Pool Loading Restrictions
NOC-AE-02001235, Submittal of Revision 15, Operations Quality Assurance Plan
CNL-20-039, Bellefonte Nuclear Plant, 1 & 2; Browns Ferry Nuclear Plant, 1 & 2; Clinch River Site; Sequoyah Nuclear Plant, 1 & 2; and Watts Bar Nuclear Station, Units 1 & 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 38
L-2020-118, Quality Assurance Program Description for 10 CFR Part 52 Licenses FPL-2 Revision 8
NG-20-0050, Response to Request for Additional Information - NextEra Energy Duane Arnold, LLC Quality Assurance Topical Report (FPL-3)
IA-86-585, Summarizes Areas to Be Inspected Per Hosgni Mods.List Tentative & Will Be Modified as Necessary Pending Completion of Licensee Sys Reviews.W/One Oversize Figure
ND-20-1415, Nuclear Development Quality Assurance Manual Version 21.0
NSD-NRC-98-5721, Informs That W Will Develop Records Retention Plan,Per Reg Guide 1.28,since Definitive Schedule for Obtaining full- Power Operating License for AP600 Does Not Exist
NSD-NRC-98-5629, Forwards Response to Facsimile from NRC Re Application of SR Coatings Inside & on Exterior of Containment.W/Response to Related ITAAC Open Item 640.186. SSAR Changes Will Be Included in SSAR Rev 22
ND-20-0256, Southern Nuclear Operating Co, Inc., Nuclear Development Quality Assurance Manual
CP-202100550, Quality Assurance Program Internal Audit Frequency
DCL-84-065, Forwards Util Response to Sser Item 57 Re NRC Questions About Qualification & Certification of HP Foley Co QC Inspectors.Info Re Qualification of Pullman Power Products QC Inspectors Will Be Provided in Near Future
NRC-88-3374, Forwards Response to NRC 880414 Questions 260.1-260.33 Re QA Program for RESAR-SP/90 Pda.Responses Reflect Discussions Between NRC & Westinghouse During Telcons & 880616 Meeting
3F1098-02, Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) by Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Into Two New Functions in ITS Table 3.3.17-1
3F0898-04, LAR 234,Rev 0 to License DPR-72,adding Three Addl Reg Guide 1.97 Type a Category 1 post-accident Monitoring Instrumentation Variables & One Type B Category 1 PAM Instrumentation Variable to Improved TS Table 3.3.17-1
AEP-NRC-2022-01, Quality Assurance Program Change Request for Internal Audit Frequency
ND-21-1116, Nuclear Development Quality Assurance Manual Version 22.0
ST-HL-AE-2093, Forwards Revised FSAR Section 3.12, Conformance W/Nrc Reg Guides. Section Updated to Reflect Util Position on All Applicable Reg Guides
CNL-22-019, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Reduction in Commitment
NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0
L-2022-068, NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 2
NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0
ST-HL-AE-1383, Forwards Rev 12 to QA Program Description, for Design & Const Phase.Rev Submitted in Accordance W/Requirements of 10CFR50.55(f)(3)
A850021, Submits Addl Info Re Rev 2 to QA Program for Operation,Per 850510 Request.Info Re Util Endorsement of ANSI N45.2.9-1974,concerning Fire Protection & Training of QC Inspectors Provided.List of Changes in Rev 2 Encl
ET-NRC-93-3795, Forwards Responses to NRC RAIs on AP600 from Ltrs 920923, 1001 & 09.Remainder of RAIs Contained in NRC Ltrs of 920923 & 1001 Will Be Provided Prior to 930123
BECO-92-067, Forwards Proposed Changes to QA Program to Eliminate Requirements Contained in QA Manual Re Involvement of QA Dept as Line Function Review
B11318, Forwards Proposed safety-related Instrument Tubing Program Presented at 840912 Meeting & Proposed FSAR Change.Review & Approval of Program Requested by 841005
ND-22-0968, Enclosure - Nuclear Development Quality Assurance Manual (Ndqam), Version 23.0
LD-88-021, Forwards Response to NRC 871208 Request for Addl Info Re Reg Guides That Appear in CESSAR-DC,QA.Suggest That Meeting W/Nrc Staff Be Scheduled to Allow Overview Program Changes
TXX-3650, Responds to NRC Re Violations Noted in Insp Repts 50-445/82-25 & 50-446/82-13 on 821122-24.Corrective Actions: Review Conducted of Inspector Certification Ltrs & Audits Re NPS Industries Reviewed.Full Compliance Achieved
TXX-6895, Forwards Addl Info to 870715 Response to Violations Noted in Insp Repts 50-445/84-32 & 50-446/84-11,based on 870715 Meeting W/Nrc.Lack of Procedures to Review Status of Const QA Program Addressed in Issue Specific Action Plan VII.a.5
TXX-6144, Forwards Responses to Violations Noted in Insp Repts 50-445/84-32 & 50-446/84-11.Corrective Actions:Qa Overview Committee Formed & Meets on Regular Basis Since Sept 1985 & Procedure DQP-CS-4 Revised
PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl
TXX-4306, Forwards Addl Info for Resolution of Open Items Re Handling of Heavy Loads,Per NRC 840830 & 0906 Requests Re NUREG-0612, Phase II
LD-92-062, Forwards Changes to Rev 7 to Topical Rept CENPD-210, Initially Submitted to NRC Via .Changes Cover QA Program,Qa Policy & Responsibilities of QA Organization
LD-92-021, Forwards Response to NRC 910806 & 1010 Requests for Addl Info,In Ref to Review of CESSAR Design Certification, Including Corresponding Revs
LD-92-031, Marked-up Copy of QA Program Topical Rept
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
LD-91-029, Forwards Rev 6 to Topical Rept CENPD-210, Description of Nuclear QA Program
TXX-3659, Forwards Final Response to NUREG-0612, Control of Heavy Loads at Nuclear Power Plants
LD-94-041, Responds to Re Violations Noted in Nonconformance Insp Rept 99900401/94-01.Corrective Actions:Purchase Order Issued to Stone & Webster Engineering Corp & Suppls Issued Cited Purchase Orders to Duke Engineering Svcs,Inc
NL-23-0444, Quality Assurance Topical Report Submittal
NRC-88-3373, Forwards Rev 11/7 to WCAP-8370/7800, Westinghouse Energy Sys Business Unit Nuclear Fuel Business Unit QA Plan
NG-20-0006, Request for Approval of NextEra Energy Duane Arnold, LLCs Quality Assurance Topical Report (FPL-3) Revision 0
B14483, Comment Supporting NRC Draft Insp Procedure 38703
NOC-AE-200036, Submittal of Operations Quality Assurance Plan Change QA-088 and Revision 24
NRC-88-3330, Forwards Rev 11/7 to WCAP-8370/7800, QA Plan. Rept Revised to Accommodate Organizational Changes
LD-89-117, Forwards Response to Request for Addl Info Re C-E QA Program & CESSAR-DC,Chapter 17,proposed Rev to CESSAR-DC & Rev 5 to CENPD-210, QA Program:Description of Nuclear Power Businesses QA Program
CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal
CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements
CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42
CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41
L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal
L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update
RAIO-0818-61388, LLC Response to NRC Request for Additional Information No. 492 (Erai No. 9551) on the NuScale Design Certification Application
RAIO-1018-62231, LLC Response to NRC Request for Additional Information No. 499 (Erai No. 9564) on the NuScale Design Certification Application
L-91-171, Forwards Annual Update of Topical QA Rept (Tqar),Consisting of Changes to Tqar,Per 900612,marked-up Version of Tqar Last Submitted,Reflecting Changes Made & Current Tqar,Including Revs Issued Through Rev 25
05000316/LER-1978-101-01, /01T-0 on 781223:both Control Room Pressurization Fans Were Inoperable.Caused by Water Seepage Into a Fire Protection Sys Switch,Resulting in Actuation of Fire Spray Sys & Lockout of the Fans
NUREG-0834, Forwards for Record,Nrc Responses to Util 811204 Comments on SER (NUREG-0843)
NL-13-2418, Vogtle Electric Generating Plant - Quality Assurance Topical Report
RAIO-1217-57599, LLC Response to NRC Request for Additional Information No. 253 (Erai No. 9184) on the NuScale Design Certification Application
L-2008-150, Point, Beach, Units 1 and 2, Quality Assurance Topical Report (QATR-FPL-1) Revisions 1 & 2
L-2006-246, Response to RAI Follow-Up Questions Regarding FPLs Common Quality Assurance Topical Report Request
NLS2006028, Report HI-2043224, Licensing Report on the Wet Fuel Storage Capacity Expansion at Cooper Nuclear Station
L-2006-143, And Duane Arnold, Supplemental Information Request for Approval of FPL Quality Assurance Topical Report
RBG-46426, Supplement to License Amendment Request (LAR) 2004-26, Use of the Fuel Building Cask Handling Crane for Dry Spent Fuel Cask Loading Operations
NL-11-1435, Vogtle Electric Generating Plant, Quality Assurance Topical Report
RAIO-1017-56676, LLC - Response to NRC Request for Additional Information No. 193 (Erai No. 9079) on the NuScale Design Certification Application
NL-24-0117, Change to Quality Assurance Program to Adopt Regulatory Guide 1.8 Revision 4 and License Amendment Request to Relocate Control of the Unit/Facility/Plant Staff Qualification Requirements from Technical Specifications to the Quality Assura
CNL-22-027, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 40
JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
L-2021-234, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 27 Update
CNL-25-010, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Response to Request for Additional Information - TVA Request for Approval of Revision 43 to TVA Fleet Quality Assurance Program Description
L-2021-098, Update to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System
NL-21-0051, Quality Assurance Topical Report, Reduction in Commitment (Pandemic Related)
L-2021-115, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 26 Annual Submittal and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 10
CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN8
CNL-24-006, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (BFN-TS-550)
NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10
RIS 2015-08, Oversight of Counterfeit, Fraudulent, and Suspect Items in the Nuclear Industry
B13245, Forwards Proposed Rev 12 to QA Program Topical Rept for Review & Approval.Changes Have Effect of Upgrading QA Program
NG-21-0028, Request for Approval of NextEra Energy Duane Arnold, LLCs Decommissioning Quality Assurance Program Revision 0
SECY-23-0041, Weekly Information Report Week Ending May 5, 2023
LD-88-033, Forwards Response to NRC 880226 Request for Addl Info on Chapter 17 to Rev 4 to Topical Rept CENPD-210A, QA Program, Including Revs to C-E 871130 & 880411 Responses
LD-95-011, Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page
CNL-25-065, Second Round Request for Additional Information - TVA Request for Approval of Revision 44 to TVA Fleet Quality Assurance Program Description
CNL-25-075, Revision to Second Round Request for Additional Information - TVA Request for Approval of Revision 44 to TVA Fleet Quality Assurance Program Description
CNL-25-059, Nuclear Quality Assurance Plan, TVA-NQA-PLN-89A, Revision 43
B12541, Rev 10 to QA Program Topical Rept
NL-25-0235, Response to Request for Additional Information Regarding Change to Quality Assurance Program to Adopt Regulatory Guide 1.8, Revision 4
L-2025-137, NextEra Energy Duane Arnold Quality Assurance Topical Report (PL-3) Revision 3