CNL-16-074, Request for Approval of an Alternative to the Inservice Examination Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI Examination Methodology Number WBN-1 & 2/PDI-4
GO2-17-210, Anchor Darling Double Disc Gate Valve Information and Status
RS-14-338, Byron/Braidwood Nuclear Stations, Updated Final Safety Analysis Report (Ufsar), Revision 15, Chapter 2.0 Site Characteristics - Braidwood
NL-16-135, Preservice Inspection Program Plan, Watts Bar Nuclear Plant, Unit 2, Program No: WBN-2 PSI Rev. 11
RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 2.0 - Site Characteristics, Table of Contents Through Table 2.5.53
NG-10-0191, NextEra Energy Duane Arnold, LLC - Supplemental Information Regarding the Duane Arnold Energy Center License Renewal Application
PLA-6603, Extended Power Uprate Master Test Procedure TP-199-013
TMI-09-101, Submittal of the Fourth Ten-Year Interval Inservice Testing Program, Revision 1, for September 23, 2004 Through September 22, 2014
PLA-6506, Submittal of Startup Test Procedures
PLA-6351, Transmittal of Startup Test Procedures Pursuant to License Conditions 2.C. (36) (B) 8 and 2.C. (36) (C)
W3F1-2006-0065, Initial Exam - 11/2006 - Licensee Post Exam Comments
ULNRC-05248, Submittal of Revision 23 to Pump and Valve Inservice Testing Program
BVY 05-023, Licensee Post Exam Comments & NRC Resolution (Folder 1)
ET 15-0022, Fourth Ten-Year Interval Submittal Snubber Program Plan and Inservice Testing Program Plan, WCOP-29, Revision 0
CNRO-2004-00014, Arkansas, Unit 1 - Request for Alternative ANO1-R&R-006, Proposed Alternative to ASME Weld Examination Requirements for Repairs Performed on Reactor Vessel Head Penetration Nozzles
L-03-057, Reply to Request for Additional Information Regarding Order EA-03-009 Relaxation Request
LR-N02-0108, Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
L-2002-044, Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-424
3F0398-10, Forwards Revised Response to NRC Re Violations Noted in Insp Rept 50-302/97-17.Corrective Actions:Revised B EDG Functional Test Procedure Safety Assessment & Revised MAR 96-11-02-01 Functional Test Procedure TP-1
JPN-88-031, Forwards Addl Info Re Local Leakage Rate Testing Corrective Action Plan,Per NRC 880511 Request for Addl Info Re 880408 Request for Exemption from Requirements of 10CFR50,App J, Section III.A.6(b)
3F0690-18, Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error
05000271/LER-1983-009-01, /01P-0:on 830321,during Refueling Outage,Planned Mods of Reactor Protection Sys Motor Generator Set Resulted in Primary Containment Isolation Sys Isolation of Ventilation Sys.Caused by Premature Removal of Slide Links
3F0110-04, Response to Request for Additional Information for the Review of the License Renewal Application & Amendment 9
LR-N05-0424, Attachment 1, Calculation S-1-SJ-MDC-1539, Revision 2, Accumulator Pressure Decay Time During Discharge Test
NUREG/CR-7288 Volume 2, Evaluation of In-Service Radon Barriers Over Uranium Mill Tailings Disposal Facilities - Appendices