L-06-055, Comment (7) Submitted by Dominion Nuclear North Anna, LLC, Eugene S. Grecheck on Supplemental Proposed Rules PR-2, 50, 51 and 52 Regarding Licenses, Certifications,. and Approvals for Nuclear Power Plants
CY-04-011, Withdrawal as Pilot Plant for Implementation of 10 CFR 50.69
05000281/LER-1999-004-02, :on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed
05000281/LER-1999-003-02, :on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP
05000281/LER-1999-001-02, :on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip
05000280/LER-2000-001, Containment Isolation Valve Found with Unacceptable Leakage During Maintenance
05000280/LER-1999-002-01, :on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
05000280/LER-1999-002, Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr
05000280/LER-1999-005-01, :on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
05000280/LER-1998-011, Forwards LER 98-011-00,per 10CFR50.73.Commitments Made in Ltr,Encl
05000280/LER-1999-006, :on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With
05000280/LER-1999-005, Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed
05000280/LER-1998-010, :on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
05000280/LER-1999-003-01, :on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With
05000280/LER-1998-012, :on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With
05000280/LER-1999-001, :on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
05000280/LER-1998-013, :on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
05000280/LER-1999-004, Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed
05000280/LER-1998-010-01, Forwards LER 98-010-01,IAW 10CFR50.73.Commitments Made by Util,Listed
05000280/LER-1998-014, :on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
05000280/LER-1999-004-01, :on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
05000281/LER-1999-002-02, :on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With
B19005, Response to Request for Additional Information Regarding Request for Exemption from the Financial Protection Requirements of 10 CFR 140.11
B19012, Response to Request for Additional Information (RAI) Regarding Realignment of Intermediate Subsidiaries
B19011, Completion Information Provided for the Order for Compensatory Measures Related to Fitness-for-Duty Enhancements Applicable to Nuclear Facility Security Force Personnel Dated April 29, 2003
B18998, Revised Response to Order for Compensatory Measures Related to Training Enhancements on Tactical and Firearms Proficiency and Physical Fitness Applicable to Armed Nuclear Power Plant Security Force Personnel Dated April 29, 2003
B18936, Implementation Status for the Compensatory Measures Related to the Access Authorization Order Dated January 7, 2003
B18863, Connecticut, Inc., Millstone Power Station, Units 2 and 3 Revised Response to Order for Interim Safeguards and Security Compensatory Measures Dated February 25, 2002
B18933, Suitability, Training and Qualification Plan, Revision 18
B18934, Physical Security Plan, Revision 45
B18861, Correspondence Distribution Request
B18873, Completion Information Provided for the Order for Compensatory Measures Related to Access Authorization Dated January 7, 2003
B18856, Additional Information Provided for Order for Compensatory Measures Related to Access Authorization Dated January 7, 2003
B18647, Request for Approval to Transmit Safeguards Information by Use of Protected Telecommunications