05000267/LER-1979-057-03, /03L-0:on 791030,during Surveillance Testing,One of Three Reactor Pressure Transmitters Found Out of Calibr. Instrument Settings Less Conservative than Required.Caused by Instrument Drift.Instrument Recalibr
05000267/LER-1982-027, Forwards LER 82-027/03L-0.Detailed Event Analysis Encl
05000267/LER-1982-040, Forwards LER 82-040/03L-0.Detailed Event Analysis Encl
NRC-99-0025, Application for Amend to License NPF-43,modifying TS SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1
LIC-97-0138, Requests Exemption from Requirements of 10CFR70.24 in Entirety for Plant,Per 10CFR70.14 & 70.24(d) as Clarified in Reg Guide 8.12
1CAN128603, Proposed Tech Specs,Incorporating Administrative Changes to Clarify Ambiguities,Remove Outdated Requirements & Provide Consistency
0CAN049602, Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Recently Approved Option B to 10CFR50,App J
B14108, Application for Amend to License NPF-49,changing TS Figure 3.1-5, Required Shutdown Margin for Mode 5 W/Rcs Loops Not Filled, Section 3.4.1.3, RCS - Hot Shutdown & 4.4.1.1.3, RCS - Hot Shutdown Surveillance Requirements
05000287/LER-1989-003-06, :on 890727,reactor Bldg Isolation Valve 3LWD-1 Returned to Svc W/O Being Leak Rate Tested Following Maint on Valve Operator.Caused by Deficient Communication Between Engineers.Leak Rate Test Performed
05000289/LER-1986-013-01, :on 861107,reactor Bldg Integrated Leak Rate Test Declared Failure as-found.Caused by Purge Exhaust & Penetration Pressurization Valve Leakage.Check & Butterfly Valves Repaired & Procedure Revised
05000267/LER-1987-011, :on 870411 & 14,unplanned Loops 1 & 2 Shutdown Occurred,Respectively.Caused by Electronic Imbalance Problem in Helium Circulator Shaft Speed Transmitter Modules & Overfilling of Liquid Monitor Dewars
05000267/LER-1987-007, :on 870310,switch Input Module (XDSH-93133) for High Reactor Bldg Pressure Channel PDSH-93133 Discovered to Be Inoperable Since 870222.Caused by Personnel Error. Supervisors Will Be Informed of Problems Found
05000267/LER-1986-009, :on 860125,one of Three Helium Circulator a Steam/Water Drain Malfunction Trip Channels Inoperable. Caused by Spare Wire Shorted to Ground Causing Power Supply Fuse Failure.Spare Wire Terminated
05000267/LER-1985-031, :on 851229,as Circulator B Cleared Out for Environ Qualification Work,No Automatic Action Occurred as Result of buffer-mid-buffer Trip Logic Actuation.Caused by Water in buffer-mid-buffer Sense Lines
05000267/LER-1985-010, :on 850720 & 28,automatic Actuation of Plant Protective Sys Actions Initiated by Primary Coolant Moisture Monitoring Sys.Caused by Misadjusted Valve Limit Switch on Differential Pressure Control Valve PDV-2549
05000267/LER-1985-008, :on 850516,plant Protective Sys Scram Circuitry Actuated by Erroneous Signal Spike on Startup Channel 1. Caused by Moisture Leakage Into Startup Channel 1 Instrument Box Resulting in Mineral Deposits
05000267/LER-1984-006, :on 840504,automatic Actuation of Plant Protective Sys Loop 1 Shutdown & Reactor Scram Circuitry Occurred.Caused by Detection of High Moisture Levels in Helium Primary Coolant
05000267/LER-1984-003, :on 840212,automatic Plant Protective Sys Reactor Scram Initiated by One of Two Logic Trips Involving Nuclear Startup Channel Ii.Caused by Insertion of Fuel Block Containing Neutron Startup Source
05000267/LER-1984-002, :on 840123,during Surveillance Test,One of Three Bearing Water Pressure Differential Switches Found Inoperable.Cause Unknown.Switch Replaced & Calibr to Instrument Operating Requirements
05000267/LER-1983-047-03, /03L-0:on 831102,one Class I Hydraulic Shock Suppressor Found Inoperable.Caused by Leaking Reservoir Gaskets Allowing Loss of Oil.Snubber Replaced W/Tested & Qualified Spare
05000267/LER-1983-040-03, /03L-0:on 830928,while Operating at 65% Power,One of Three Loop II Plant Protective Sys Dewpoint Moisture Monitors Discovered Inoperable Due to Overheating of Mirror. Caused by Slight Pressure Decrease in Monitor
05000267/LER-1983-038-03, /03L-0:on 830927,during Scheduled Surveillance Testing on Circulator 1C Circuitry,A Logic CT-2A2 Module Found Inoperable.Caused by Loose Connection in Logic Module. Module Replaced
05000267/LER-1977-043-03, Region Outlet Temp of One Region Exceeded Tech Spec Limit.Caused by Small Lateral Movements of Fuel Columns.Core Region Constraint Installed
05000267/LER-1981-047-03, During Testing,One of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Dirt Accumulation in Electrical Switch.Switch Replaced
05000267/LER-1982-047-03, /03L-0:on 821201,during Surveillance Testing on Loss of Bearing Water Plant Protection Sys Circuitry for Circulator C,Logic a Module CT2 Found Inoperable.Caused by Failure of Chip Z-32 in Logic Module CT-2A2.Chip Replaced
05000267/LER-1978-035-03, /03L-0 on 781114:4 of 6 High Pwr Rod W/Drawal Prohibit Trip Points Were Set Too High.Accepted Test Procedure Voltage Range Permitted RWP to Be Set Higher than Tech Specs Allow
05000267/LER-1978-032-03, /03L-0:on 780928,surveillance Check of Fixed Low Flow Alarm Bistables for Primary Coolant Dew Point Moisture Monitors Not Performed.Caused by Misinterpretation of Surveillance Requirements
05000267/LER-1978-025-01, /01X-1:on 780703,w/loss of Power to One of Two Redundant Logic Sys,Circulator Seal Malfunctioned & buffer- to-mid-buffer Trip of Helium Circulator Initiated.Caused by Logic Design Problem
05000267/LER-1982-025, Forwards LER 82-025/03L-1.Detailed Event Analysis Encl
05000267/LER-1982-002, Forwards LER 82-002/03L-0.Detailed Event Analysis Encl
05000267/LER-1982-003, Forwards LER 82-003/03L-0.Detailed Event Analysis Encl
05000267/LER-1982-002-03, /03L-0:on 820121,during Surveillance Testing, W/Reactor Shut Down,Three Loss of Bearing Water Pressure Differential Switches Found W/Setpoints Less Conservative than Required.Caused by Instrument Drift.Switches Recalibr
05000267/LER-1981-073, Forwards LER 81-073/03L-0.Detailed Event Analysis Encl
05000267/LER-1981-070, Forwards LER 81-070/03L-0.Detailed Event Analysis Encl
05000267/LER-1981-055, Forwards LER 81-055/03L-0.Detailed Event Analysis Encl
1CAN039006, Forwards Evaluation of Reactor Bldg Coolers Svc Water Isolation Valve
05000267/LER-1981-047, Forwards LER 81-047/03L-0.Detailed Event Analysis Encl
LR-N18-0028, Submittal of Emergency Plan Document Revision Implemented December 6, 2017 and January 30, 2018
05000267/LER-1981-018-03, /03L-0:on 810214,sample Flow Alarm Setpoints of Three Dewpoint Moisture Monitors Found Outside Tech Spec. Probably Caused by Previous Misadjustment.Trip Points Readjusted
05000267/LER-1981-018, Forwards LER 81-018/03L-0.Detailed Event Analysis Encl
05000267/LER-1981-010-03, /03L-0:on 810120,five Sample Flow Circuits Found Out of Calibr.Caused by Change of Instrument Characteristics.Calibr Values Revised & Flow Transmitters Recalibr.Alarm Setpoint Functional Test Values Also Changed
05000267/LER-1981-005-03, /03L-0:on 810107,during Surveillance Testing,Trip Setting on PDIS-21177 Bearing Water Differential Pressure Switch Found Below Tech Spec Limit.Caused by Instrument Drift.Switch Adjusted & Returned to Svc
05000267/LER-1981-024, Forwards LER 81-024/03L-0.Detailed Event Analysis Encl
05000267/LER-1981-012-03, /03L-0:on 810127,six of Twelve Steam Pipe Rupture (Pipe Cavity)Ultrasonic Noise Channels Had Unacceptably Low Response to Known Noise Source During Test.Caused by Microphone &/Or Transmitter Gain Reduced to Stop Tripping
05000267/LER-1980-048-03, /03L-0:on 800901,during Surveillance Test,All Six Ultrasonic Noise Channels Were Found Inoperable.Microphone &/Or Transmitter Gain Had Been Reduced to Spurious Trips. Cause Not Stated.Gain Returned to Acceptable Levels
05000267/LER-1987-014, :on 870504,during Drain Line Radiography, Loop 2 Shutdown Initiated Due to High Count Rate & Turbine Tripped from Low Main Steam Temp.Caused by Inadequate Radiographic Administrative Controls
05000267/LER-1978-033-03, /03L-0 on 781027:during Routing Surveillance of Steam Pipe Rupture Detection Sys,One of Three Bistables for High Temperature Under Pcrv Did Not Trip,Due to Corroded Cable Terminal Board at Junction Box
05000267/LER-1980-024-03, /03L-0:on 800512,at 47% Thermal power,1C Circulator Seal Differential Pressure Decreased Significantly Due to Unknown Causes.Equalizing Valve Closed & 1C Circulator Buffer Helium Pressure Returned to Normal
05000267/LER-1980-021-03, /03L-0:on 800421,w/reactor Shut Down,Main Steam Pressure Low Instrument Discovered Inoperable.Caused by Bad Connection Due to Dirty Contact.Contacts Cleaned & Module Returned to Svc
05000267/LER-1980-018-03, /03L-0:on 800327,w/plant Operating at Approx 51% Thermal Power,One Loop 2 Hot Reheat Header Activity Monitor Found Inoperable.Caused by Failure of Motorola Chip (MPS-66A)in Operational Amplifier to Detector Preamp
05000267/LER-1980-013-03, /03L-0:on 800310,during 58% Thermal Power Operation,Indicated Flow for Two Low Level Primary Coolant Dewpoint Moisture Monitors Discovered Less than Requirements.Caused by Inaccurate Flow Elements
05000267/LER-1980-008-03, /03L-0:on 800219,during Routine Surveillance Testing,Setpoints for Low Flow on One Dewpoint Moisture Monitor & for Fixed low-low Flow on Another Monitor Found Less than Min Acceptable.Caused by Instrument Calibr Drift
05000267/LER-1979-023-03, /03L-0 on 790727:while Performing Normal Surveillance,Fixed Feedwater Low Flow Switch Found Inoperable. Caused by Component Failure from Normal Wear. Module Was Repaired,Reinstalled & Retested Satisfactorily
05000267/LER-1980-002-03, /03L-0:on 800107,during Region Constraint Device Installation,Found That Startup Channel Scram Protection Not Operable at Less That or Equal to 100,000 Counts/Second. Caused by Improper Setpoints.Setpoint Change Initiated
05000267/LER-1979-060-03, /03L-0:on 791128,during Maint Shutdown,Found Bearing Water Pressure Differential Switches W/Setpoints Less Conservative than Tech Specs.Caused by Instrument Drift.Switches Readjusted
05000267/LER-1979-062-03, /03L-0:on 791201,during Routine Surveillance Testing,Three Moisture Monitor Flow Transmitters Found Out of Tolerance.Caused by Instrument Calibr Drift.Transmitters Recalibr & Retested Successfully
05000267/LER-1979-046-03, /03L-0:on 791011,noted That Sequence of Manual Switching of Primary Coolant Low Level Dew Point Moisture Monitors Can Result in Degraded Mode of Limiting Conditions for Operation.Sys Operating Procedure Revised
05000251/LER-1987-007-01, :on 870310,air Leakage During Leak Rate Testing of Personnel Hatch Exceeded Tech Spec Requirements.Caused by Malfunctioning Equilizing Valve Not Being Able to Fully Close.Valve Replaced
L-76-344, Letter Informing the NRC That FP&L Has Reviewed Inspection Report 05000335/1976010 and Has Determined That It Contains No Proprietary Information
LIC-04-0117, License Amendment Request, Revisions of Technical Specifications Table 1-1 and Section 4.0
ONS-2017-006, Emergency Plan Revision 2016-003