0CAN100303, Response to NRC Inspection Report 50-313, 368/03-11
IA-84-291, Advises That Use as Is Disposition Acceptable,Based on Review of Daniel Intl Welding Procedure Spec Technique Sheet Number N-8-8-A-4,Rev 0,for Welding w/3/32-inch Electrode Using 105 Amperage
ST-HL-AE-1457, Forwards Response to Draft SER & FSAR Items for Chapter 12 Re Radiation Monitoring & Protection.Encl marked-up FSAR Pages Will Be Incorporated in Future Amend Unless Otherwise Noted
SNRC-1900, Suppl to 920113 Application for Amend to License NPF-82, Authorizing Long Island Power Authority to Implement Decommissioning Plan.Suppl Consists of Revised NSHC Analysis
SNRC-1835, Advises That Util Does Not Plan to Provide Written Responses to Generic Ltr 91-06 Nor Generic Ltr 88-20,Suppl 4 Since Util No Longer Holder of Ol,Per NRC Issuance of Amend 7 to License NPF-82 on 910614,transforming OL to Pol
05000424/LER-1988-004-01, :on 880201,containment Hydrogen Monitor Control Room Indication & Alarm Inoperable Due to Reversal of Signal Wire Leads at Cabinet.Caused by Personnel Error.Technician Counseled & Procedure Revised
05000498/LER-1988-013, :on 880204,two Time Delay Relays in solid-state Protection Sys Not Tested During Surveillance.Caused by Inadequate Review of Vendor Technical Manual & Actuation Logic Schematics.Procedure Revised
05000251/LER-1986-010-01, :on 860425,during Performance of Periodic Test Load on 4A 4-kV Bus,Breaker 4AA20 Failed to Close.Caused by Breaker Position Switch 52HH Not Being Actuated.Position Switch Replaced W/Redesigned Actuator & Guide
AECM-88-0107, Forwards Computer Tape of Hourly Meteorological Data for 1987.Note Tape Formatted Similar to Tape Sent Earlier by Ltr Except That Ebcdic Format Rather than Ascii Format Used.Sample Tape Dump Printout Also Encl
05000461/LER-1988-006, :on 880229,Div II Containment Exhaust Process Radiation Monitor Tripped to low-fail Condition.Caused by Personnel Error Due to Inadequate Accessibility & Visibility of Detector.Existing Scaffolding Replaced
05000387/LER-1984-044, :on 840613,average Rod Scram Insertion Time Required by Tech Spec 3.1.3.4 Not Met for All Rods. Apparently Caused by Poor Control Rod Scram Pilot Valve Performance.Valves Modified
W3P88-0967, Forwards Revised Attachments 2 & 3 to Updated QA Program Description,Fsar Chapter 17.2 to Aid in Review
B15959, Forwards Root Cause Evaluation rept-effectiveness of Oversight Organization Per Evaluation Conducted in May 1996. More Contact Between Chief Nuclear Officer & Line Mgt Recommended
AECM-85-0196, Forwards Addl Info Requested in 850613 Telcon to Support Review of Results of 850423-25 Safety/Relief (SRV) in-plant Test Submitted on 850606.Location of Installed SRV in-plant Test Instrumentation & Real Time Data Provided
05000282/LER-1992-013, :on 920925,main Generator Was Taken Off Line & Turbine Manually Tripped.Caused by Equipment Failure.Failed Detector Replaced & Source Range Channel 1N-31 Tested Satisfactorily
05000423/LER-1992-015, :on 920523,discovered That Containment Leakage in Excess of Limits Due to Valve Leakage.Hinge & Packing Cleaned & Lubricated
LD-84-069, Forwards marked-up CESSAR FSAR Pages Reflecting Review of Tech Specs Re First Sys 80 Plant.Rev Involves Interface Requirements for MSIV & Main Feedwater Isolation Valve Closure Time
05000423/LER-1992-001, :on 920113,leaking Monitoring Connection Containment Isolation Valves Were Not Locked Closed.Caused by Program failure-procedure Deficiency & Administrative Error.Valves Were Locked Closed
05000237/LER-1976-041-01, /01T-0:on 760616,reactor High Pressure Scram Switches Ps 2-263-55C & a Found to Actuate Above Tech Spec Limit.Caused by Instrument Setpoint Drift.Both Switches Reset.Switch Recalibr Scheduled for Next Month
B15266, Notifies NRC of Inability to Completely Satisfy Requirements for Second 10-yr ISI Augmented Exam of Reactor Pressure Vessel at Millstone Unit 2 & Requests Authorization to Not Perform Any Addl or Alternative Exams
05000327/LER-1983-031-01, /01T-0:on 830311,RPI for Control Rod D-14 of Shutdown Bank a Declared Inoperable Due to False Indication. Caused by Open RPI Circuit Due to Connector Failure & Thermal Expansion.Rpi Connector Replaced
05000237/LER-1982-035-03, /03L-0:on 820724,offgas Flow Indicated High During Normal Startup.Caused by Cracked Fillet Weld in 2D1 Feedwater Heater Emergency Spill to Normal Heater Drain Line Connection.Weld Cracked Due to Excessive Line Movement
05000364/LER-1982-008-03, /03L-0:on 820226,instrumentation Loop Associated w/LI-485 (Steam Generator B Level Indication) Declared Inoperable When Reading Was Out of Tolerance W/Other Channels.Caused by Obstruction in Ref Leg
B14458, Forwards Suppl Info to 930330 Application for Amend to License NPF-49 Re Several 18-month SR for Surveillances Listed in Table 1 of Submittal to Be Performed During Fourth Refueling Outage Presently Scheduled to Begin on 930731
05000409/LER-1981-010-01, /01T-0:on 810923,during Normal Operation Mechanical Interlock Preventing Simultaneous Opening of Both Doors of Containment Bldg Personnel Airlock Failed.Caused by Worn or Misadjusted Actuating Mechanism.Drawings Encl
AECM-81-312, Forwards Proposed FSAR Changes & Additions,Response to Auxiliary Sys Branch Question 10.29 & Discussion of Perched Aquifer Recharging.Proposed FSAR Changes Will Be Incorporated in Next Available Amend
BECO-91-025, Provides Semiannual Rept for long-term Program,Including Schedules for a & B Regulatory Items,Commitment Descriptions & Progress Since Last Update
05000316/LER-1982-112-03, /03L-0:on 821220,during Refueling Shutdown,Fire Door 374 Unable to Close Properly When Both Leaves of Double Door Opened.Caused by Damaged Sequencer,Due to Unknown Origin.Sequencer Replaced
RBG-38320, Forwards Rev 0 to Topical Rept EA-PT-91-0003-S3, Thermal/ Hydraulic Analysis Nuclear Engineering Section Engineering Dept River Bend Nuclear Group Gulf States Utils
NUREG-0227, Partial Draft of Nuclear Power Plant Operating Experience - 1978, Section 3.0, Plant Outages. Portions of NUREG-0483, NUREG-0366 & NUREG-0227 (Plant Operating Experience for 1977,1976 & 1974-75,respectively) Encl
L-5590-443, Radiological Environ Monitoring Rept,1978
L-91-117, 1990 Annual Radiological Environ Operating Rept St Lucie Plant Units 1 & 2
L-81-340, Responds to NRC Re Violations Noted in IE Insp Rept 50-335/81-14.No Proprietary Info.Corrective Actions: Double Posting on Solid Surface Implemented in Areas Where Postings Can Be Removed
L-85-397, Advises That Util Will Provide Response to NRC 850621 & 0711 Requests for Info Re Relief & Safety Valve Test Requirements Per TMI Item II.D.1 by 860315
05000333/LER-1991-006-01, :on 910507,manual Reactor Shutdown Occurred Due to Inoperability of Both Low Pressure Coolant Injection Subsystems.Caused Mechancial Failure of One Valve in Each of Two Sys.Root Cause Investigation Started
05000361/LER-1983-060-01, /01T-0:on 830529,hourly Instead of Continuous Fire Watch Established & Backup Fire Suppression Equipment in Place Until Zone 5 Deluge Water Spray Sys Returned to Svc. Caused by Inadequate Procedures