L-PI-16-038, ISFSI - Transmittal of 2015 Annual Radiological Environmental Monitoring Program Report
L-PI-15-039, ISFSI - 2014 Annual Radioloqical Environmental Monitoring Program (REMP) Report
BSEP 18-0039, Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D
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
NL-09-1510, Vogtle Electric Generating Plant, Units 1 and 2 - Inservice Inspection Plan Third Inspection Interval Volume 1, Version 3.0
NL-08-0877, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) Application of Dissimilar Weld Full-Structural Weld Overlays Alternative Lsi ALT-08-02 Version 1
NL-08-0280, Application of a Dissimilar Metal Weld Full-Structural Weld Overlay
NL-07-1320, Proposed Alternative or Application of Pressurizer Nozzle Full-Structural Weld Overlays
NOC-AE-07002104, Response to NRC Request for Additional Information on Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation
NL-07-0366, Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays - Revision 2.0
NL-06-2768, Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays and Response to Request for Additional Information
NL-06-1713, Proposed Alternative for Application of Pressurizer Nozzle Full-Structural Weld Overlays
NRC-2013-0217, Federal Register Notice: Maine Yankee Atomic Power Company, Connecticut Yankee Atomic Power Company, and Yankee Atomic Electric Company Notice of Granting Exemption from 10 CFR 50.38 Requirements
NL-02-160, Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, & 5.0 of Improved TS
NL-02-159, November 2002 Monthly Operating Report for Indian Point Unit 2
L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report
B12307, Clarifies 860312 Request for Exemption from Type C Testing Requirements of 10CFR50,App J for Reactor Coolant Charging Penetration P-8.Util Intends to Evaluate Mods to P-8 Pending Results of Integrated Assessment
B12136, Forwards Revised Pages to Attachments 2 & 3 of Re 10CFR50,App J Exemption Request Concerning Testing of Containment Isolation Valve in Reverse Direction & Addition of Penetration Requiring Schedular Exemption
NG-97-1597, Forwards Response to Request for Addl Info on Improved Tech Spec Change Re Not Entering LCO Action Statements During Certain Surveillances
A05946, Forwards Response to Open Items Identified During 860508 Meeting Re Proposed Rev to Pump & Valve Inservice Testing Program.Rev IWV-1 Table for Valve Testing Program, Description of ECCS Full Flow Test & Insp Procedure Encl
PY-CEI-NRR-1384, Semiannual Radioactive Effluent Release Rept for 1991: Quarters 1 & 2
05000344/LER-1987-023, :on 870826,increasing Water Level in Steam Generator C Led to Turbine Trip on hi-hi Level Isolation Signal.Caused by Failure of Feedwater Regulating Valve C to Close.Valve Local Operator Procedures Reviewed
05000334/LER-1997-040, :on 971210,inadequate Testing of Reactor Protection Sys P-8 Interlock,Was Identified.Caused by Vendor Design Error.Applicable Surveillance Test Procedures Were Revised to Include Manual Test
L-81-535, Submits Integrated Startup Test Program for Insp & Testing to Be Completed Prior to Returning Unit to Operation After Steam Generator Repair Program,Per Amend 69 to Ol.Apps A,B, C & D Encl
RA06-038, Post-Outage 90-Day Inservice Inspection Summary Report
L-2002-165, Response to NRC Request for Additional Information for Review of the License Renewal Application
RA-24-0264, Proposed In-service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzle N4D
DCL-12-083, Response to Request for Additional Information on License Amendment Request for Digital Process Protection System Replacement