L-76-230, Forwards Impingement of Aquatic Organisms - March 1976 and Impingement of Aquatic Organisms - April 1976
L-76-221, Letter Regarding Condition E.3 to the Operating License and Attaching the Westinghouse Review of the Design of the Fan Cooler Motors and a Table Comparing the WCAP-7829 Test Machine Motors
L-77-293, 9/19/1977 Letter Endorsement Nos. 17 & 18 to Maelu Policy MS-59 Representing Nuclear Energy Liability (Suppliers and Transporters Form) Coverage at Turkey Point and St. Lucie Plants
L-77-381, Letter Transmitting Revision 1 to Steam Generator Repair Report Which Was Forwarded on 9/20/1977
05000316/LER-2076-006, Letter Abnormal Environmental Occurrence of Total Chlorine Residual Not Determined During Chlorination Cycle Due to Chemical Technician Being Involved in Other Analysis and Losing Track of Time
L-76-283, Letter Advising Florida Power & Light Company Recently Has Recently Become a Full Participating Member of Nuclear Plant Reliability Data System, & Is Expending Effort Necessary for Full Implementation of This Voluntary Program
L-76-392, Submittal of Environmental Technical Specification Reports Entitled Impingement of Aquatic Organisms - August, 1976 & Impingement of Aquatic Organisms - September, 1976
L-76-243, Letter Regarding Conditions of License and Requesting That Authorization for Operation Beyond June 30, 1976 Be Granted
L-76-434, Submit Supplemental Information Concerning Steam Generator Tube Integrity Questions
L-77-259, Transmitting Reports of Changes, Tests, and Experiments Which Covers the Period July 1, l976 Through June 30, 1977
L-76-439, Letter Transmitting Supplemental Information Related to Previous Submission of 12/9/1976 Regarding ECCS Reevaluation
L-77-303, 9/26/1977 Letter Endorsement Nos. 16 and 17 to Nelia Policy NS-308 Representing Nuclear Energy Liability (Suppliers and Transporters Form) Coverage at Turkey Point and St. Lucie Plants
L-76-238, Letter Transmitting Supplemental Information Related to Evaluation of Spent Fuel Transfer Process Submittal of 6/23/1976
L-76-438, Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt
L-76-106, Letter Enclosing a Construction Incident Report Relating to Low Fluid Levels in Six Hydraulic Seismic Snubbers
L-76-433, Response to Request to Evaluate Effects of Increased Fission Gas Releases on Safety Analysis, Submit Westinghouse Letter NS-CE-1302 Dated 12/2/1976 as FPL Position for the Subject
L-77-434, Answers to Question Nos. 2 and 7 and Revised Answers to Questions 8 and 9 Pertaining to the Steam Generators Tube Integrity Supplemental Information
L-77-187, 9/23/1977 Letter Endorsement Nos. 15 and 16 to Maelu Policy MS-59, Representing Nuclear Energy Liability (Suppliers and Transporters Form) Coverage at Turkey Point and St. Lucie Plants
L-76-418, Transmittal of Request to Amend Appendix a of Facility Operating License
L-77-200, Forwarding Final Inservice Inspection Reports
L-77-188, 6/23/1977 Letter Endorsement. Nos. 35 and 36 to Policy No. MF-55 Representing Nuclear Energy Liability Coverage at Turkey Point Plant
L-77-113, Letter Re Reactor Vessel Fracture Toughness Requirements & Weld Metal Surveillance Data
L-77-317, Letter Referring to Letter Dated October 5, 1977 Concerning Indemnity Agreement to Policy No. MF-88 and Enclosing a Letter Dated February 24, 1977 and Attached Endorsement Nos. 12, 13 and 14
05000289/LER-1976-046, Forwards LER 76-046/01T.Provides Supplemental Info
05000259/LER-2076-020, Drywell Temperature Recorder TR-64-52 Became Erratic During Startup Testing
05000296/LER-2077-010, For Browns Ferry Nuclear Plant, Unit 3, HPCI Turbine Steam Supply Valve 3-FCV-73-16 Failed to Open During Performance of an Operability Surveillance Instruction
05000296/LER-2077-007, For Browns Ferry Nuclear Plant, Unit 3, Torus Oxygen Sensor O2M-76-42 Failed to Calibrate to 2-Percent Oxygen Calibration Gas During Normal Operation
05000259/LER-2077-001, Relief Valve on Pump Discharge Opened at Lower than Set Pressure During Performance of Surveillance Instruction 4.4.A.1 on Standby Liquid Control Pump 3A
05000260/LER-2077-004, For Browns Ferry Nuclear Plant, Unit 2, Two Heat Detectors in the Fire Protection System for the Recirculation MG Sets Which, Would Not Alarm
05000259/LER-2077-002, HPCI Restraints R-24 & R-35 on Pump Discharge Line Were Discovered with Loose Bolts & Broken Cinch Anchors Upon Completion of Operation of HPCI System During Reactor Scram on 1/26/1977
05000259/LER-2076-008, Neutron Monitoring Battery 2A Was Inoperable When Connector Was Accidentally Broken Off Cell Post During Routine Cleaning
05000259/LER-2077-007, Torus Oxygen Sensor O2M-76-42 Failed to Calibrate to 2-percent Oxygen Calibration Gas During Normal Operation
05000259/LER-2076-010, Error by Licensed Operator in Pulling out-of-sequence Control Rod During Scram Time Testing
05000296/LER-2077-013, For Browns Ferry Nuclear Plant, Unit 3, SLC Pump 3A Discharge Relief Valve Lifted at 1275 Psig During Surveillance Testing When Pump Was Started Against Throttled Test Valve Set at That Pressure
L-76-200, Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons
L-77-193, Letter Affidavit for Proposal to Change Figure 21.1-1 of Technical Specifications
05000316/LER-2076-011, And LER-1976-011-00 for Donald C. Cook, Unit 1 - Ice Buildup Around Two Ice Condenser Intermediate Deck Doors, and Failure of Wind Direction Recorder
05000316/LER-2076-009, Re Failure of Wind Speed & Direction Indication & LER 1976-009-00 Re Failure of Wind Direction System at Microwave Tower
05000316/LER-2076-053, Re Containment Air Particulate & Radio Gas Monitor (R-11 & R-12) Pump Failing to Run
05000316/LER-2076-027, Re Mode 1 Position, Containment Air Particulate Detector Pump Would Not Run
05000316/LER-2076-019, & LER 1976-019-00 for Donald C. Cook, Unit 1 One Accelerometer Out of Three Found Movable Mass Hard-Up Against Stops & Reactor Coolant System Pressure Increasing
05000316/LER-2076-052, Re Iodine Spike Following Power Transient
05000316/LER-2076-021, Quadrant Power Tilt of 1.023 Was Calculated Using the Excore Nuclear Instrumentation Readings
05000316/LER-2076-036, Re Failure of C-D Diesel Generator to Start on Two Successive Attempts During Surveillance Test
05000316/LER-2076-057, Motor Operated Suction Valve Found in Closed Position When Performing Normal Valve Lineup Check Prior to Starting West Containment Spray Pump
05000316/LER-2077-019, Higher than Normal Casing Temperature of W Centrifugal Charging Pump
05000316/LER-2077-024, Electrical Failure of Valve QMO-201, Charging Header Isolation
05000316/LER-2077-036, Pump Failure Leading to Inoperability of Radiation Monitoring Channel R-11/12
05000316/LER-2076-059, Iodine Spike Following Power Transient, Violation of Limit Specified in Technical Specification 3.4.8
05000316/LER-2077-023, Two Instances of Failure to Have Temporary Changes Reviewed by the Pnsrc and Approved by the Plant Manager in Violation of Appendix a Technical Specification 6.8.3.c
05000316/LER-2077-033, Position Indication for Rod F-6 Indicating a 33 Step Deviation from Bank Position
05000316/LER-2077-017, Discovery of Inoperability of 50 Foot Wind Direction Recorder
05000316/LER-2077-010, D.C Cook Unit 1 - LER 1977-010-00 Re Three Inoperable Safety Valves on Steam Generator
05000316/LER-2076-054, Concerning Rod F-6 Position Indication Found to Be in Excess of Tech Spec Limits
05000244/LER-2076-007, For R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch
05000244/LER-2078-009, For R. E. Ginna, Bus 18 Breaker from a Emergency Generator Overcurrent Relay
05000244/LER-2076-008, For R. E. Ginna, Abnormal Degradation of Steam Generator Tubes
05000244/LER-2076-029, R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition
05000244/LER-2076-012, Containment Personnel Airlock Handwheel Shaft Seal Excessive Leakage During Testing
05000244/LER-2076-027, R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line
L-77-392, Combustion Engineering Reported Potential CEA-to-Guide-Tube Interaction That Lead to Deterioration of Guide Tube. FP&L Implemented Weekly Cycling of CEAs as Requested by NRC Per Phone Conversation on 12/23/1977. Will Prepare .
L-76-415, Forwards Preoperational Test Procedure No. 0700080B,, Steam Generator Feedwater Hammer Test
L-76-414, Letter Enclosure of Generic Report on Overpressure Protection for Operating CE Ness
L-76-437, Florida Power & Light Co.S Response to NRCs Letter of 8/1/1976 Concerning Anticipated Transients Without Scram
05000335/LER-2076-018, During Performance of Control Element Assembly Calibration Preoperational Test, RCS Boron Concentration Was Diluted and Group I Was Inserted to Match Reactivity
05000335/LER-2077-006, With the Plant Operating at Power, Control Element Assembly 60 Dropped, Initiating Turbine Run Back and Giving a Rod Bottomed Indication
05000335/LER-2076-047, Steam Driven Auxiliary Feedwater Pump Would Not Start Because Trip Solenoid Latch Failed to Engage
05000335/LER-2077-007, During Routine Surveillance, CEA 7 Was Found to Be Inoperable. CEA 7 Is a Shutdown CEA
05000335/LER-1977-015, For Saint Lucie Unit 1 Regarding Failure of the 1A Diesel Generator to Start During a Surveillance Test
05000335/LER-2076-004, For Saint Lucie Unit 1, a Breach of Containment Integrity
05000335/LER-2076-036, Steam Driven Auxiliary Feedwater Pump Would Not Start Because Steam Supply Valve Would Not Open Fully
05000335/LER-2076-005, For St. Lucie Unit 1, Two Inoperable Containment Area Radiation Monitoring Instrumentation Channels
05000335/LER-2076-003, For St. Lucie Unit 1, a Design Error in Engineered Safety Features Actuation System
05000335/LER-2076-032, Relief Valve in Boric Acid Make-Up System Developed a Leak
05000335/LER-2076-001, For St. Lucie Unit 1, a Breach of Containment Integrity
05000335/LER-2076-002, For St. Lucie Unit 1, Spent Fuel Crane Overload Interlock-Setpoint Drift
05000335/LER-2077-005, Two Main Feed Pump Discharge Valves Could Reopen After Closing on a Main Steam Isolation Signal
05000335/LER-2076-044, With 1B Diesel Generator Out of Service for Preventive Maintenance on Air Line Lubricators, 1A Diesel Generator Failed to Start During Surveillance Test
05000335/LER-2076-042, With Reactor Shutdown for Fuel Inspection, Containment Purge Fan Was Started and Sufficient Vacuum Was Obtained to Cause Containment Vacuum Release Valve to Open
05000335/LER-2076-028, Review of the Testing Proposed for Unit 2 Hydrogen Sampling System Isolation Valves Led to Examination of Purchase Order for the Identical Unit 1 Valves
05000237/LER-1977-016, For Dresden Unit 2 Regarding an Incident Concerning the Torque Switch on the Limitorque Operator for Recirculation Pump Suction Valve MO-2-202-4B Opened and Prevented the Valve from Closing While Isolating the B Recirc
05000237/LER-1977-023, For Dresden Unit 2 Regarding Discovery of the 12% APRM Upscale Rod Block Trip Setting to Be at 12.5% for APRM Channel One Due to Setpoint Drift
05000237/LER-1977-027, Regarding Failure of 46 Control Rod Drives to Fully Insert and Latch at Position 00 Following a Reactor Scram on July 9, 1977
05000220/LER-1977-022, For Nine Mile Point Unit 1 Regarding Discovery of Linear Indications on Three Collet Retainer Tubes in Drive Mechanisms Removed from the Reactor Vessel
05000220/LER-1977-028, For Nine Mile Point Unit 1 Regarding Failure of a Reactor Low Water Level Instrument to Trip When Tested
05000237/LER-1977-017, For Dresden Unit 2 Regarding Discovery of the Ball Isolation Valve on E Traversing Incore Probe (TIP) System Guide Tube to Open from the Control Room
05000237/LER-1976-074, For Dresden Unit 2 Regarding a Control Rod J-2 Withdrawal of One Notch and Reactivity Inserted by This Resulted in a Transient Power Increase
05000237/LER-1977-024, For Regarding the Inoperability of the Unit 2/3 Diesel Generator for 25 Minutes on June 30, 1977
05000220/LER-1977-029, 77-030-00, 77-031-00, 77-034-00, & 77-035-00 for Nine Mile Point Unit 1 Low-Low-Low Level Set Point Out of Specs on RE-18A, Vacuum Switch Trip & Reset Point on Torus Relief Valves Out of Specs, Weld Leak in Emergency Condenser
L-79-157, Submits Figure of Max Predicted Heat Flux (Fq) for Cycle 6, Based on 18-case Analysis of ECCS
L-79-148, Notifies of Reduction in Allowable Peak Linear Heat Rate in Accordance w/790526 & 27 Telcon W/P Erickson.Reduction Necessitates Change in Tech Specs.Revised Figures Encl