Nonmetallic Thermal Insulation for Austenitic Stainless Steel
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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
L-2016-129, NextEra Energy Quality Assurance Topical Report (QATR FPL-1) Revision 19 Annual Submittal
RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5
RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5
RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5
L-2015-184, Units 1 and 2, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 17
L-14-244, Reply to Request for Additional Information for the Review of License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 52
L-2014-201, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 14
RS-14-130, Responses to NRC Requests for Additional Information, Set 18, Dated April 10, 2014, Related to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application
RS-14-003, Bryon, Units 1 and 2, Response to NRC Requests for Additional Information, Set 2, Dated December 13, 2013, Related to the License Renewal Application
L-2013-208, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 13
ULNRC-05886, Enclosure 1, Responses to the Individual Requests Contained in July 5, 2012 RAIs and Enclosure 2, Contains LRA Amendment 5 to Reflect Changes Made as a Result of the RAI Responses
L-2011-243, Submittal of Quality Assurance Topical Report (QATR FPL-1), Revision 9
L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 5, Reactor Coolant System
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 4, Reactor
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 10, Steam and Power Conversion System
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
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, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65)
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 10.0 - Steam and Power Conversion System
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 6.0, Engineered Safety Features
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
L-2010-138, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 7
NL-09-1510, Vogtle Electric Generation Plant, Unit 2 - 3rd Interval VOGTLE-2 ISI Plan, Version 3.0
NL-09-1510, Vogtle Electric Generation Plant, Unit 1 - Third 10-Year Interval ISI Plan, Version 3.0
L-2009-134, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 4
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 6.0 - Engineered Safety Features
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
W3F1-2007-0046, Request for Alternative W3-ISI-005, Request to Use ASME Code Case N-716
CNRO-2006-00043, Request for Alternative GG-ISI-002, Request to Use ASME Code Case N-716
L-2006-208, Plants - Response to Request for Additional Information Regarding Common Quality Assurance Topical Report
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
RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description
L-2019-134, Units 1 and 2 - Quality Assurance Topical Report, Revision 22, Annual Submittal
CP-201900467, (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings
HNP-05-101, Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage No Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
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
PLA-5724, Proposed Relief Request No. RR-27 to the Second 10-Year Inservice Inspection Program
BSEP 04-0007, Request to Use ASME Boiler and Pressure Vessel Code Case N-663
NL-03-183, Stations - Relief Request to Use ASME Code Case N-663
CNRO-2002-00056, Request to Use ASME Code Case N-663 for Arkansas Nuclear One, Unit 1, Waterford, Unit 3, Grand Gulf, and River Bend Station
M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems
DCL-84-029, Forwards Info Re Testing of Carboline Protective Coatings Used in Containment Bldgs,In Response to NRC 831205 Request at Meeting Concerning QC Program for Painting (Sser 21,Allegation 100)
JAFP-86-0770, Annual Summary of Changes,Tests & Experiments for 1985
RC-98-0207, Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment
ULNRC-03916, Forwards Util 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CCS After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. Supporting Info,Encl
BVY-97-137, Forwards Response to 971009 RAI Re Plans for Implementing ASME Code Case N560 at Vermont Yankee Nuclear Power Station
BVY-97-105, Provides NRC W/Degradation Mechanism Evaluation & Results of Element & Segment Risk Rankings.Util Intends to Submit Revised ISI Program Following NRC Review of Evaluations & Risk Ranking,As Stated in Ltr
ST-HL-AE-1710, Forwards marked-up FSAR Pages Re Deletion of Containment Spray Sump Additive Tank.Requests NRC Review Changes as Soon as Possible to Avoid Impacting Project Schedule
NG-75-1559, Forwards Responses to NRC Questions Re 750613 Rept on Wetted Insulation & Lagging Following Reactor Coolant Pump C Seal Failure.Summary of Piping & Insulation Insp to Be Performed During Next Refueling Outage Encl
TXX-4462, Forwards Revised Method for Temporary Changes Made to Plant Procedures.All Temporary Changes to Procedures Which Do Not Change Intent of Approved Procedures Will Be Approved by Two Members of Station Mgt Staff
LD-88-099, Responds to NRC Request for Addl Info Re Chapters 5 & 9 of CESSAR-DC Re Steam Generator Secondary Water Chemistry, Reactor Coolant Water Chemistry,Fire Protection Sys,Letdown Purification Line & Hydrogen Ignition
LD-91-071, Responds to NRC Requests for Addl Info for Review of C-E SSAR-Design Certification Rept.Proposed Revs to SSAR Encl
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
L-24-207, License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 1
NG-88-0424, 1987 Annual Rept of Facility Changes,Tests,Experiments & Safety & Relief Valve Failures & Challenges
NG-20-0006, Request for Approval of NextEra Energy Duane Arnold, LLCs Quality Assurance Topical Report (FPL-3) Revision 0
AECM-81-394, Forwards Identified & Recommended Corrections to NUREG-0831, Facility Ser.Errors Consist Primarily of Technical Errors & Clarification Affecting Correctness of Rept
AECM-82-358, Forwards Comments & Status of Util Review of OL & Ser.Info Provided to Assist in Generation of Fourth Suppl to SER & Full Power OL
LD-90-008, Forwards Response to 881216 Request for Addl Info Re CESSAR-DC,Chapters 3,4,5 & 6 Re Turbine Missiles,Control Element Drive Structural Matls,Cleaning & Contamination Protection Procedures & Reactor Internals Matls
05000285/LER-1980-010-01, /01T-0:on 800516,during Cold Pressure Test,Leakage Discovered at Gasket Joint Between Pump Casing & Pump Cover on Reactor Coolant Pumps RC-3A,3B & 3C.Closure Studs Corroded by Boric Acid.Leaks Caused by Deteriorated Gaskets
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
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
GO2-98-071, Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi
05000244/LER-1979-023-01, During Inservice Insp, Liquid Penetrant Examination of Pressurizer nozzle-to-safe- End Weld Showed Linear Indications.Caused by Inadequate Delta Ferrite Content & Geometric Discontinuity
3F1209-12, Response to Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application (TAC No. ME0274) and Amendment 8
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
B19021, ASME Section XI Inservice Inspection Program Request to Use Code Case N-663 as Alternative
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-2021-115, 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
RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5
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
L-87-365, Changes,Tests & Experiments Made W/O Prior Commission Approval,For Jul 1986 - June 1987
RBG-27108, Forwards Suppl Rept of Safety Evaluations for Documents Only Changes Included in USAR for Mar 1986 - Feb 1987