NL-12-2269, SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 11
RS-12-154, Attachment 2 - Heat Transfer Calculations Used to Develop Attachment 5 and Table A5-1 in the July 12, 2012, License Amendment Request
NL-09-1510, Vogtle Electric Generating Plant, Units 1 and 2 - Inservice Inspection Plan Third Inspection Interval Volume 1, Version 3.0
NRC-94-0022, Forwards Application for Renewal of NPDES Permit MI0037028 for Fermi 2,per Section 3.2 of Fermi 2 Environ Protection Plan
RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process
JAFP-85-0226, Monthly Operating Rept for Feb 1985
HL-4669, Comment Supporting Petition for Rulemaking PRM-9-2 Filed by Ohio Citizens for Responsible Energy,Inc
BECO-91-045, Annual Dose Assessment to General Public from Radioactive Effluents,1990
05000325/LER-1997-011-01, :on 970912,identified Unanalyzed Pressure Suppression Flow Due to Simultaneous Drywell & Suppression of Chamber Valve Lineups.Caused by Insufficient Detailed Documentation.Completed Revs to Operating Procedures
0CAN048604, Submits Update of Tasks Performed Over Past 6 Months in Response to NUREG-0737 Suppl 1 (Generic Ltr 82-33) Re Crdr, Reg Guide 1.97,emergency Operating Procedures & Spds.Revised Integrated Implementation Plan Encl
05000454/LER-1997-019, :on 971028,potential Failure of W Fuel Were Noted.Caused by Inadequate Methods & Incorrect Assumptions in Fuel Rod Design Code.W Has Developed Comprehensive Plan to Resolve Fuel Rod Internal Pressure Issue
05000424/LER-1988-014, :on 880425,Tech Spec Surveillance Test Not Performed within Required Time Interval.Caused by Personnel Error & Inadequate Communications.Personnel Involved Counseled Re Use of Overdue Rept
05000374/LER-1985-026-03, :on 850522,diesel Generator 2B Tripped Approx 3 After Being Started Per Surveillance Procedure.Caused by Time Delay Relay for Low Lube Oil Pressure Switch Not Operating Correctly
05000395/LER-1992-003, :on 920520,reactor Trip Occurred During Repair of Nuclear Instrumentation Due to Personnel Error.Personnel Completed Repair Activity Which Initiated Trip & Verified Operability of NI-42 Before Plant Restart
05000247/LER-1984-021, :on 841002,during Surveillance Test of Svc Water Pumps,Back Leakage Across Check Valves on Discharge Side of Two Pumps Observed.Affected Check Valves Repaired & Tested Satisfactorily
05000317/LER-1983-016-03, /03L-0:on 830328,during Transfer of Resin from Miscellaneous Waste Ion Exchanger to Solid Waste,Hole Developed in Sight Glass for Resin Transfer Line.Caused by Attempt to Open Resin Clog.Piping Mods Developed
05000282/LER-1982-022-03, /03L-0:on 821112,during Power Operation,Control Power Lost to Diesel Cooling Water Pump 22,rendering Pump Inoperable.Caused by Loose Fuse Clip.Clip Repaired & Pump Tested Satisfactorily
05000338/LER-1990-004, :on 900312,discovered That 31-day Dose Projections for Liquid and Gaseous Releases Not Performed During 1989 Per Tech Specs 3.11.1.3 & 3.11.2.4.Caused by Personnel Error.Personnel Counseled
3F1089-23, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 174 Re Proposed Heatup,Cooldown & Inservice Leak & Hydrostatic Testing Pressure/Temp Limits. Rept Re Low Temp Overpressure Protection Withheld
05000325/LER-1980-043-03, /03L-0:on 800422,while Securing Diesel Generator Number 4,control Power to Diesel Was Lost.Caused by Shorting Together of Unit Available Bulb Contacts & Blowing of Control Power Fuse.New Bulb Installed & Fuse Replaced
L-88-256, Forwards Rev 11 to Fpltqar 1-76A, Topical QA Rept & marked-up Rev 10.Revs Are Organizational Changes
A07899, Provides Addl Info Re Undervoltage Detection Mods & Related License Amend Request,Per NRC 890320 Request.Actual Wiring Drawings Represent True Indication of Separation & Redundancy & Design Single Failure Proof
05000338/LER-1990-001, :on 900123,reactor Trip Occurred on Steam Feedwater Flow Mismatch.Caused by Failed Circuit Driver Card on Feedwater Regulating Valve.Feedwater Regulating Valve Driver Card Replaced
A06401, Forwards Responses to Questions on Pumps & Valves Inservice Testing Program,Per 870602 & 03 Meetings
05000424/LER-1991-003-03, :on 910222,during Relay Testing RHR Sys Containment Sump Suction Valve Opened.Caused by Electrical Ground on stem-mounted Limit Switch.Ground Condition Will Be Examined,Confirmed & Corrected