NL-16-0169, Enclosure 8: Hatch Standard Emergency Plan Annex
NL-16-0169, Enclosure 6: Farley Justification Matrix
NL-15-1392, Enclosure 9 - Hatch Justification Matrix
NL-15-1392, Enclosure 6 - Farley Justification Matrix
NL-11-032, Indian Point, Units 2 & 3, Response to Request for Additional Information on Aging Management Programs
ULNRC-05269, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238)
NL-03-2383, Inservice Inspection Summary Report
B12232, Forwards Addl Info Re Inservice Testing of Emergency Diesel Generator Auxiliary Sys Revised Relief Request & Pump/Valve Tables,In Support of Review of Inservice Testing Program. Response to NRC 860723 Questions Also Encl
NG-96-2574, Responds to 961118 Telcon RAI Re Inservice Insp Relief Requests NDE-020 & NDE-R011.Ultrasonic Calibr Data,Provided
AECM-88-0225, Forwards Annual Rept on Form 10-K for 1987,quarterly Rept on Form 10-Q for Quarter Ending June 1988 & Annual Rept to Shareholders for 1987,per Util 881019 Proposed Amend to License NPF-29 Re Sale & Leaseback Transaction
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
B11566, Forwards Seismic Adequacy Evaluation of Gas Turbine Control House Electrical Equipment Anchorage Committed in Util .Mods to Strip Chart Recorder Instrument Rack Will Be Installed by End of 1985 Refueling Outage
AECM-83-0210, Forwards Revised FSAR App 13A,incorporating Staff Changes Involving Key Personnel.Info Will Be Incorporated Into Next FSAR Amend
05000413/LER-1988-019, :on 880425,valid Failure of Diesel Generator 1A Occurred Due to Faulty Oil Pressure Sensor.Caused by Design, Mfg,Const/Installation Deficiency.Components Known or Suspected to Have Failed Replaced & Tested
W3P88-0967, Forwards Revised Attachments 2 & 3 to Updated QA Program Description,Fsar Chapter 17.2 to Aid in Review
3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability
05000395/LER-1984-002, :on 840111,hourly Roving Fire Watch Patrol for Auxiliary Bldg Not Performed During Previous 8 H Per Tech Spec.Caused by Personnel Error.Roving Fire Watches Now Verifying Required Checks W/Shift Supervisor
05000219/LER-1981-062-03, /03L-0:on 811125,core Spray Hi Drywell Pressure Switch RV46C Tripped in Excess of Tech Spec Limit.Caused by Sensor Repeatability.Sensor Recalibr
05000325/LER-1979-033-03, /03L-0 on 790513:unable to Perform Daily Surveillance to Verify That Power Ratio & Peaking Factor Do Not Exceed Specified Values.Caused by Computer Analog Scanning Sys.Sys Calibr & Returned to Svc
05000333/LER-1980-004-03, /03L-0:on 800107,during Surveillance Testing,One of Four Core Spray Injection Permissive Switches Found to Be Set Approx 10 Psi Below Tech Spec Limit.Caused by Instrument Drift.Switch Recalibr
L-98-065, Forwards Revised Epips,Including 0-EPIP-20106, Natural Emergencies, 0-EPIP-20132, Technical Support Center Activation & Operation, & 0-EPIP-20133, Operations Support Center Activation & Operation
L-92-035, Monthly Operating Repts for Jan 1992 for Turkey Point,Units 3 & 4
L-14-243, Seventeenth Refueling Outage Inservice Inspection Summary Report
SVPLTR 10-0037, 2011 Dresden Nuclear Power Station Initial Examination Outline Submittal
NL-07-0276, National Pollutant Discharge Elimination System (NPDES) Permit Renewal
W3P87-2060, Forwards Changes to QA Program (FSAR Section 17.2) Re Significant Transition at Facility from Const to Operations Phase Which Included Major Reorganization of Nuclear Operations Dept.Fee Paid