DCL-12-069, Diablo Canyon, Units 1 and 2 - Process Protection System Replacement Interface Requirements Specification (Irs), Revision 6, Attachment 3
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
3F0185-01, Forwards Conceptual Design to Control Complex Dedicated HVAC Cooling Sys for Safe Shutdown Panel,Power Supply & Switchgear,Per 10CFR50 App R,In Response to 830106 Request
W3P84-1695, Forwards Updated Operator Shift Experience Form,In Response to 840523 Request.Options for Satisfying Shift Operating Experience Requirements at 5% Power Listed.Resumes Encl
BECO-LTR-96-043, Radiological Environ Monitoring Program Rept No 28,Jan-Dec 1995
W3P84-3337, Forwards Addl Info on Soil Spring Distributions & north- South Bending Capacities in Positive & Negative Directions Re Foundation Basemat Cracks,Per Js Ma 841116,20 & 26 Requests
05000245/LER-1987-012, :on 870519,overhead Fireproofing Blanket Matl Over Emergency Diesel Generator (EDG) Found to Be Inadequate to Provide 3 H Fire Resistance Rating.Cause Unknown.Fire Watch Established & Firecoating Installed
05000344/LER-1987-036, :on 871202,seismic Monitoring Instrumentation Surveillance Missed.Caused by Personnel Error.Required Surveillance Performed & Seismic Monitoring Instrumentation Verified Operable
05000354/LER-1986-069, :on 860924,full Reactor Scram Originating from Nuclear Instrumentation Sys Occurred.Caused by Spurious Inoperative Trip of Intermediate Range Monitor G.Testing Procedures Will Be Revised
05000440/LER-1986-086, :on 861126,reactor Scram Occurred Due to Upscale Trip on intermediate-range Neutron Monitors.Caused by Personnel Error & Procedure Deficiency.Instruction Revised & Operators Retrained
05000440/LER-1986-083, :on 861119,reactor Protection Sys Actuation Occurred as Result of Installation of Jumper Across High Pressure Relay.Caused by Deficiency Re Testability of Equipment.Relays Modified & Instruction Revised
05000366/LER-1986-018, :on 860810,RWCU Isolated on High Differential Flow Signal.Caused by Failure to Fill & Vent RWCU Resin Trap &/Or Resin Trap Isolation Valves Being Partially Open. Demineralization Procedure & Valves Modified
05000354/LER-1986-066, :on 860907,discovered That Surveillance Testing of Main Turbine Bypass Valve Not Performed Prior to Increasing Reactor Power Above 25%.Caused by Procedural Inadequacy.Surveillance Test Procedure Revised
05000155/LER-1986-006-01, :on 860825,fire Barrier Determined to Be Nonfunctional & Fire Watch Not Established within 1 H.Caused by Procedural Inadequacy.Procedure Modified to Clarify Definition of Nonfunctional Fire Barriers
05000255/LER-1986-038, :on 861108,while in Cold Shutdown,Radioactive Liquid Effluent Release Occurred.Caused by Shift Supervisor Error.Shift Supervisors Counseled
05000354/LER-1987-022, :on 870509,cooling Tower Blowdown Radiation Monitoring Sys Sample Pump Found Out of Svc for Greater than 12 H & Required Grab Samples Not Taken.Caused by Personnel Error.Technician Counseled & Retrained
05000354/LER-1986-079, :on 861019,automatic Isolation of RWCU Sys from Invalid High Differential Flow Signal Occurred.Caused by Differential Flow Indication Being in Error Due to Entrapped Air in Sensing Lines.Valve Repaired
05000410/LER-1987-012, :on 870208,MSIV Closure Occurred on Low Condenser Vacuum Signal.Caused by Unusual & Complicated Set of Conditions That Precluded Running Surveillance Test W/O Adverse Consequences.Test Procedure Revised
05000255/LER-1987-001-01, :on 870114,containment Penetrations Associated W/Containment Hydrogen Monitoring Sys Did Not Employ Redundant Isolation Logic.Caused by Sys Design Description Not Being Implemented as Prescribed
05000255/LER-1986-013, :on 860225,reactor Protection Sys Actuation Occurred from Spike in Nuclear Instrument Channel.Caused by Reenergization of Preferred Ac Bus During Manual Transfer. Procedural Controls Instituted
05000302/LER-1988-020, :on 881012,hydraulic Snubber RCH-81 Found Disconnected at Piping End.Snubber Removed to Allow Maint on Adjacent Valve on 871119.Snubber Reinstalled.Procedure Revised for Tracking Purpose
05000416/LER-1988-019, :on 881010,HPCS Sys Inadvertently Injected, Resulting in Reactor Scram on Low Water Level.Caused by Actuation of Channels C & G of Reactor Low Water Level HPCS Initiation Logic Due to Radio Transmission
05000482/LER-1988-018, :on 881011,fuel Bldg Ventilation Isolation Signal & Control Room Ventilation Isolation Signal Received from Fuel Bldg Exhaust Radiation Monitor.Caused by Failed Radiation Monitor Signal Cable
05000275/LER-1986-013, :on 860913,three Snubbers on Steam Generator 1-2 Discovered W/Load Pins Out of Position.Most Likely Caused by Mispositioning of Pin.Upgraded Locking Device & Set Screws Installed
05000387/LER-1985-027, :on 850809,offgas Pretreatment Radiation Monitors Declared Inoperable.Caused by Determination That Tech Spec 4.3.7.11-1.4 Surveillance Requirement Not Met.New Surveillance Procedures Prepared
05000373/LER-1986-021-02, :on 860608,ESF Actuation of HVAC Emergency make-up Train B Occurred Due to Spurious Radiation Monitor Trip.Cause Attributed to Electronics Problem W/Radiation Detector 2D18-K751D.Detector Replaced
05000458/LER-1986-033, :on 860426,reactor Scrammed Due to Combination of Planned half-scram from Surveillance Test & Unplanned half-scram.Caused by Blown Fuse in Reactor Protection Sys. Fuse Replaced
05000277/LER-1988-008, :on 880328,failure to Submit Special Rept Re Inoperability of Cardox Sys in Control Room on Time Determined.Caused by Lack of Programmatic Controls.Limiting Condition for Operation Instructions Revised
05000259/LER-1988-042-01, :on 881029,unplanned ESF Actuation Occurred. Caused by Failure of Personnel to Ensure That Work Plan Sufficiently Addressed Effects on Plant Equipment.Work Plan Specifying ESF Actuations Revised
05000423/LER-1986-008, :on 860202,turbine Bldg Ventilation Stack Radiation Monitors Out of Svc & 12 H Grab Samples Required by Tech Spec Action Statement 3.3.3.10 Not Taken.Caused by Chemistry Dept Error.Samples Taken
05000278/LER-1988-004-02, :on 880613,discovered That Dampers in Emergency Bus Room Ventilation Duct Penetration Would Not Close.Caused by Ventilation Diffuser Located in Damper Track.Fire Watch in 4 Kv Switchgear Room Continued
05000333/LER-1988-002, :on 880310,RCIC Made Inoperable for Approx 1 Minute Due to Automatic Closure of Steam Supply Valve While HPCI Inoperable.Caused by Failure to Follow Procedures.Rcic Restored to Svc
05000414/LER-1988-019-01, :on 880527,reactor Trip During Cycle of Alternate Source to Kxpb Breaker,Recommended by Control Room Operator to Clear Undervoltage Condition.Caused by Mgt & Design Deficiency.Util Stabilized in Mode 3
05000354/LER-1988-001-01, :on 880106 & 28,liguid & Gaseous Radwaste Discharge Monitors Failed to Pass Functional Tests.Caused by Design & Procedure Deficiencies.Gaseous Radwaste Monitor Surveillance Procedures Revised
05000293/LER-1988-009, :on 880304,documentation for Completion of Surveillance Procedure 8.9.13 Not Located for Diesel Generator B.Cause Undetermined.Operating Supervisor Required to Log Initiation & Completion of Tests
05000498/LER-1988-010, :on 870923,maint Work Request Prepared Stating That Charging Header Pressure Indicator Reading 1,000 Psi More than Local Process Pressure Gauge.Caused by Lack of Identification in Tech Spec Re Subj Loop
05000247/LER-1985-009, :on 850920,short Circuit Between Phases of Main Transformer Caused Turbine Generator Trip.Caused by River Water Spray from Condenser Water Box Exhaust.Changes Made to Exhaust to Eliminate Spray
05000323/LER-1986-001-01, :on 860102,automatic Reactor & Turbine Trip Occurred Due to lo-lo Steam Generator Water Level.Caused by Main Feedwater Pump Trip During Full Load Rejection Startup Test.Pump Control Oil Sys Flushed
05000482/LER-1985-084, :on 851210,during Routine Update of Surveillance Data Base,Violation of Tech Spec 4.0.2b Re Allowable Time Intervals Discovered.Caused by Logic Error in Computer Program.Program Corrected
05000458/LER-1985-014, :on 851018,standby Cooling Tower Level Discovered Below Min Tech Spec Requirement of 78%.Caused by Operator Error During Manual Operations of Standby Svc Water Sys.Procedure SOP-0018 Revised
05000255/LER-1985-025, :on 851130,during Hot Shutdown at 0% Power, Electrical Equipment Not Enviromentally Qualified Became Administratively Inoperable.Unusual Event Secured When Cold Shutdown Attained on 851201
05000255/LER-1984-017, :on 840903,LPSI Flow Control Valve CV-3006 (Fcv:Bp) Not Fully Open.Caused by Misadjusted Packing During Refurbishing of Valve in 1983 & 1984
05000331/LER-1985-032, :on 850802,plant Operated for Period in Excess of 7 H W/O Performing Required Surveillance in Neutron Noise Region.Caused by Operator Error.Personnel Counseled
05000373/LER-1985-053-01, :on 850717,RHR Shutdown Cooling High Suction Flow Switches 1E31-NO12AA/AB/BA/BB Discovered Piped in Reverse of Sys Design & Inoperable.Caused by Failure to Revise Design Drawing.Drawing & Piping Revised
05000373/LER-1985-054-01, :on 850718,process Radiation Monitors Registered off-scale High,Actuating Control Room Emergency Makeup Filter Train B.Caused by Defective Procedure. Procedure Revised & Submitted for Approval
05000271/LER-1985-008, :on 850928,error in Offsite Dose Rate Calculation Procedure Discovered.Caused by Use of Incorrect Equation.Procedure Corrected & Dose Rate Calculated for Worst Case During 850401-0909
05000322/LER-1985-038, :on 850908,water Level Indicator Associated W/Ref Leg B Read High & Diverged from Water Level Indicators Associated W/Ref Leg A.Caused by Excess Condensate Accumulation in Steam Line
05000316/LER-1985-025-01, :on 850906,discovered That Reactor Trip Instrumentation Surveillance Requirements 4.3.1.1.1,Items 18B & 20 Inadequate.Cause Not Determined.Items Added to Computerized Nuclear Test Schedule for Reactor Startup
05000315/LER-1985-022, :on 850502 & 04-07,during Refueling,High Alarms Received on Lower Containment Monitor Particulate Channels ERS-1301 & ERS-1401.Caused by Fluctuation Activity Resulting in Erroneous Alarms.Value Will Be Updated
05000498/LER-1992-010, :on 920808,standby Train a CCW Pump Started Due Sensed Low Pressure on Miscellaneous Supply Header.Caused by Lack of Procedural Guidance.Surveillance Procedure & Sys Operating Procedure Revised
05000269/LER-1985-005-01, :on 850411,reactor Tripped from 100% Full Power Upon Closure of Low Pressure Turbine Intercept Valves & Main Turbine Control Valves.Caused by High Turbine Header Pressure & Reduced Heat Transfer
05000374/LER-1984-070, :on 841009,door to Main Steam Tunnel on 687 Ft Elevation of Auxiliary Bldg Found Unsecured & Held Open by Ventilation Flow.Caused by Personnel Error.Employee Counseled & Contractor Personnel Trained
05000348/LER-1984-021, :on 841008,hourly Fire Watch Not Conducted in Accordance W/Tech Spec 3.3.3.9 When Fire Alarm for Svc Water Intake Structure Cut Out.Caused by Personnel Error.Personnel Counseled & Fire Alarm Returned to Svc
05000269/LER-1985-001-01, :on 850111,one of Two Trains of Engineered Safeguards Sys Rendered Inoperable Due to Loss of Power Supply in Engineered Safeguards Protection Sys Cabinet. Caused by Failed Electrolyte Capacitor
05000364/LER-1984-010-01, :on 840915,steam Generator 2A Steam Flow Channel F1-475 Not Tripped Until 4 H After Channel Declared Inoperable.Caused by Personnel Error.Transmitter Equalizing Valve Closed
05000373/LER-1985-025-01, :on 850304,drywell Vacuum Breaker Cycled Open & Closed.Caused by Steam from RCIC Turbine Causing Temp/ Pressure in Suppression Pool to Rise.Breaker Operated as Required
05000237/LER-1985-006-04, :on 850217,reactor Scram Occurred During Undervoltage Tests.Caused by Misunderstanding of Ae Re Power Supply Divisionalization.Power Supplies Will Be Redesigned, Rewired & Tested
05000271/LER-1985-003, :on 850131,monthly River Water Samples Scheduled to Be Collected During Wk Ending 850113 Were Collected 850124,contrary to Tech Specs.Caused by Personnel Error.Surveillance Requirements Reviewed by Personnel
05000373/LER-1985-011-01, :on 850202,group 1 Isolation Occurred Due to High Main Steam Tunnel Ambient Air Temp,Causing Reactor Scram.Caused by Lack of Ventilation Flow to Steam Tunnel. Isolation Dampers Repaired
05000388/LER-1984-013-01, :on 840726,during Scram Due to Turbine Control Valve Fast Closure & Deenergization of 13.8 Kv & 14.16 Kv Buses,Control Rods Did Not Fully Insert.Caused by Failure of Diesel Generators to Start Automatically
05000255/LER-1984-007-01, :on 840622,work on Pressure Indicator Caused Number of Spurious Actuations of Low Temp Overpressure Protection Sys.Caused by Personnel Error.Proper Communication & Job Coordination Emphasized
05000364/LER-1995-006, :on 950622,determined That Analysis of RCS Dose Equivalent Iodine (Dei) Analysis Not Performed Per TS SR 4.4.9 Due Cognitive Personnel Error.Dei Analysis Completed on 950622 & Personnel Reinstructed
05000289/LER-1991-006-01, :on 911104,discovered Increased Potential for post-LOCA Boron Precipitation.Caused by Error in NSSS Vendor Licensing Basis Analysis.Util Will Confirm Calculations to Support Conclusions within 1 Month
05000267/LER-1984-004, :on 840327,surveillance Test Requirements for SR 5.2.23,firewater Booster Pump Surveillance,Not Performed in Conjunction W/Sr 5.2.7a-A,water Turbine Drive Surveillance.Caused by Procedural Inadequacy
05000255/LER-1983-052-01, /01T-0:on 830804,w/safety Injection Tank T-82D Inoperable Due to Routine Evolution,Second Safety Injection Tank T-82B Became Inoperable Due to Low Level.Caused by Leakage Past Fill & Drain Valve
05000373/LER-1984-002-03, :on 840106,unit Scrammed on Low Water Level Following Trip of Turbine Driven Reactor Feed Pump on High Seal Temp.Caused by Failed Flow Controller Which Regulates Seal Water Temp.Controller Replaced
05000416/LER-1991-005, :on 910617,fault Occurred on B-phase of Breaker J5232 (500 Kv).Caused by Inadequate Maint Practices.High Pressure Tank Replaced & Three Adjacent High Pressure Tanks within B-phase Inspected & Cleaned
05000285/LER-1991-014, :on 910629,radiation Monitor RM-054A Discovered Out of Svc.Caused by Personnel Error.Test OP-ST-SHIFT-0001 Revised to Include check-off When All Radiation Monitors Calibrated
05000280/LER-1982-087-03, /03L-0:on 820901 & 20,pump 1-SW-P-10A Experienced Loss of Suction Power & on 820901,14 & 20,pump 1-SW-P-10A Experienced Similar Loss of Suction.Cause Due to Insufficient Npsh.Svc Water Replaced.Svc Water Pumps Vented
05000282/LER-1990-013, :on 900830,inadvertent Mispositioning of Control Switch of 11 Shield Bldg Ventilation Heater Controls Identified.Caused by Workman Unknowingly Moving Switch. Protective Covers Installed Over Switches
05000280/LER-1982-096-03, /03L-0:on 820916,w/unit at 99% power,PT-27C Revealed That Amp Readings for Heat Tracing Panel 9,circuit 19,was Below Acceptance Criteria.Caused by Excessive Heat. Defective Heat Tracing Replaced & Tested
05000272/LER-1982-027-99, During Surveillance Testing,Fire Pump 2 Did Not Start in Automatic Mode & Declared Inoperable.Caused by Damaged Flywheel.Flywheel Repaired
05000414/LER-1989-010-03, :on 880314,auxiliary Feedwater Pump 2A Discharge to Steam Generator 2A Isolation Failed to Completely Close.Caused by Design Deficiency.Mods to Actuator Torque Switch Setting Increased
05000413/LER-1989-030-01, :on 890726,Tech Spec Violation Occurred Due to Shipment of Two Liners of Secondary Bead & Powdex Resin Mixture.On 891215,same Tech Spec Violation Occurred.Caused by Mgt Deficiency.Shipments Suspended
05000311/LER-1990-015, :on 900415,ESF Signal Actuation for Containment Ventilation Isolation Occurred.Caused by Procedural Inadequacy.Setpoint Setting Modified & Detector Time Constant Extended from 20 to 40
05000306/LER-1989-004-02, :on 891221,unit Tripped & Reactor Coolant Pumps Lost Power.Caused by Faulty Voltage Regulation of One CRD Mechanism motor-generator Set.Regulator for Set Replaced & Tested.On 891226,identical Trip Occurred
L-2014-154, Response to Request for Additional Information Regarding License Amendment Request No. 216 - Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor
TMI-11-061, ISI Program Plan, Fourth Ten-Year Inspection Interval
05000275/LER-1987-002, :on 870222,reactor Tripped Due to High Steam Generator Water Level.Caused by Calibr Drift of Electrical Current to Pressure Converter,Preventing Steam Generator Valve from Opening.Converter Recalibr