ULNRC-06349, Callaway, Unit 1 - Enclosure 3 to ULNRC-06349 - Document A22-1690-001, Rev. 0, Decommissioning Cost Analysis for the Callaway Energy Center, Appendix C, Page 4 of 10 - Appendix E, Page 7 of 10
RC-15-0020, Attachment 3 - Final NDE Inspection Reports
NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 13 of 14
L-2010-259, St. Lucie, Unit 1 - License Amendment Request Extended Power Uprate, Attachment 9; Core Operating Limits Report (Colr) Markups
BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves
LR-N09-0014, Submittal of Biennial Decommissioning Funding Status Report
CP-201300040, Comanche Peak, Units 1 and 2 - Transmittal of Year 2012 Radiological Environmental Operating Report
L-87-362, Responds to NRC Re Violations Noted in Insp Repts 50-250/87-25 & 50-251/87-29.Util Withholding Payment of Proposed Civil Penalty Until Notified of Resolution of Access & Search Issues.Security Plan Mgt Being Improved
NG-96-2344, Forwards NRC Form 474, Simulator Facility Certification, Due to Changes in Performance Testing Plan,Per 10CFR55.45. Description of Performance Tests Completed from Apr 1995 to Apr 1996 & Performance Test Schedule for 1996-1999,encl
CNL-21-081, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(b) and the Use of Case N-526
LIC-95-0202, Responds to NRC Re Violations Noted in Insp Rept 50-285/95-14 on 950813-0923.Corrective Actions:Contractor Craft on Site Given Remedial Training on SO-G-107 Requirements
3F1095-09, Clarifies Commitment for Use of self-contained Breathing Apparatus by Crystal River Unit 3 Control Room Operators During Event Involving Toxic Gas
SNRC-1008, Forwards List of Active Safety-Related Equipment at Qualification Level, Per SER Issue 8, Dynamic Qualification & Util 821123 Commitment
CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.
PY-CEI-NRR-1533, Responds to Violations Noted in Insp Rept 50-440/92-11 on 920527-0615.Corrective Actions:Fill & Vent Summary Sheet, Containing Instruments from All Three RHR Loops,Will Be Eliminated & Operations Personnel Will Be Trained
05000320/LER-1988-011, :on 880807,control Room Personnel Failed to Recognize Requirements to Enter Action Statement.Caused by Misunderstanding of Requirements of Tech Spec 3.8.1.1. Event Discussed W/Operators
3F0496-27, Forwards Interoffice Correspondence Dtd 960422,documenting Evaluation of Test Data Against Curve.Calculation Encl
05000255/LER-1975-027, :on 751221,discharge Temp Exceeded Tech Spec Temp Differential Limit When Cooling Tower a Removed from Svc. Caused by Slow Valve Closing Time Which Does Not Prevent Weir Overflow Following Pump Trip
05000348/LER-1981-045-03, /03L-0:on 810613,train Svc Water Loop a Declared Inoperable.Caused by Inoperable Emergency Recirculation Valve Due to Blown Control Circuit Fuse.Fuse Replaced,Valve Tested & Loop Returned to Svc on 810613
05000334/LER-1981-062-03, /03L-0:on 810619,auxiliary Flow Path to Steam Generator 1A Was Isolated.Caused by Maint on Leaking Feed Flow Transmitter Instrument Line Penetration Into Auxiliary Feed Flow Header A.Piping Refabricated
RS-18-098, Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from .
GO2-12-019, 2011 Annual Financial Report
BW040017, Tenth Refueling Outage Steam Generator Inservice Inspection Summary Report
CY-02-064, Annual Radioactive Effluent Report for January Through December 2001
NL-05-0211, Inservice Testing Program Summary for the Interval July 1, 1994 Through April 6.2006. Revision 3
RS-06-039, Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors