ONS-2015-088, Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-004, Limited Visual Examinations from 1 EOC27, 2EOC26 and 3EOC27 Outages
DCL-15-038, Response to NRC Request for Additional Information Regarding Relief Request REP-SI - Part 2
DCL-15-021, Response to NRC Request for Additional Information Regarding Relief Request RES-SI
RS-14-338, Byron/Braidwood Nuclear Stations, Updated Final Safety Analysis Report (Ufsar), Revision 15, Chapter 2.0 Site Characteristics - Braidwood
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 15.0 - Accident Analyses, Pages 15-i - 15.3-76
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 1 of 9
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 2.0 - Site Characteristics, Table of Contents Through Table 2.5-35
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
05000482/LER-1985-049, :on 850709,ESF Actuation & Reactor Trip Occurred Due to lo-lo Water Level in Steam Generator C. Caused by Loss of Feedwater Flow Due to Installation & Removal of Test Equipment.Personnel Counseled
A01877, Forwards Station Procedures OP 302,SP 631.1,SP 631.2, Sp 631.4,SP 631.11,SP 1051,IC 414c,WP-1-24,CNF-7995-4, CNF-F-FFB & CNF-FF & One Oversize Drawing in Response to NRC .Aperture Card Will Be in PDR
05000272/LER-1990-020-01, :on 900608,identified That maint-I&C Procedures for Setting Intermediate Range Excore Nuclear Instrumentation Sys Permissive P-6 Not Correct.Caused by Inadequate Procedure Control
NLS2008067, Response to Nuclear Regulatory Commission Request for Additional Information Reactor Equipment Cooling System
Information Notice 1998-21, Potential Deficiency of Electrical Cable/Connection Systems