0CAN041702, Annual Radioactive Effluent Release Report for 2016
PNP 2017-013, 2016 Radiological Environmental Operating Report
0CAN101701, Units 1 and 2, Revised Annual Radiological Environmental Operating Report for 2016
0CAN051604, Annual Radiological Environmental Operating Report for 2015
PNP 2016-029, ISFSI - Transmittal of 2015 Radiological Environmental Operating Report
0CAN051502, Annual Radiological Environmental Operating Report for 2014
0CAN081405, Units 1 and 2 - Correction to Annual Radiological Environmental Operating Report for 2012
PNP 2013-037, 2012 Radiological Environmental Operating Report
PNP 2012-033, Submittal of 2011 Radiological Environmental Operating Report
PNP 2011-037, & ISFSI, Submittal of 2010 Radiological Environmental Operating Report
0CAN041102, Annual Radiological Environmental Operating Report for 2010
M180071, GEH Vnc Written Follow-Up Report - Ntr Control Room Staff
PNP 2018-019, 2017 Radiological Environmental Operating Report
0CAN051001, Annual Radiological Environment Operating Report for 2009
0CAN050803, ISFSI - Annual Radiological Environmental Operating Report for 2007
0CAN050603, Annual Radiological Environmental Operating Report for 2005
M190063, GEH - Submittal of Annual Nuclear Test Reactor (Ntr) Operating Report for the Year 2018
0CAN041903, Submittal of Annual Radioactive Effluent Release Report for 2018
PNP 2019-014, 2018 Radiological Environmental Operating Report
05000280/LER-2078-009-03, L Re Snubber Body in Contact with Structure; LER 1978-009-03L Re Trip of Boric Acid Transfer Pump; & LER 1978-010-03L Re Failure of Pressurizer Channel
05000280/LER-1976-002, Updated LER 76-02/01T:on 760313,determined Worst Break LOCA Core Thermal Transient Analysis Inaccurate Since Effects of Steam Generator Tube Plugging on LOCA Not Considered
05000281/LER-1976-003, Updated LER 76-03/01T:on 760521,routine Chemistry Analysis of Primary Coolant Boron Concentration Indicated Unplanned Dilution Occurred.Caused by Three Tubes Cut on Steam Generator 2A.Tubes Plugged
0CAN052001, Annual Radiological Environmental Operating Report for 2019
M210030, GEH Ntr Written Report to EN 55113- Requalification Program Due Date Exceedance
M210041, GEH Annual Nuclear Test Reactor (Ntr) Operating Report for the Year 2020
0CAN052101, Annual Radiological Environmental Operating Report for 2020
0CAN052201, Annual Radiological Environmental Operating Report for 2021
0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022
0CAN050901, Annual Radiological Environmental Operating Report for 2008
0CAN052401, – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 2023
PNP 2023-013, 2022 Radiological Environmental Operating Report
0CAN041407, Annual Radiological Environmental Operating Report for 2013
PNP 2014-041, 2013 Radiological Environmental Operating Report
05000270/LER-1983-002-03, Computer Became Inoperable Causing Loss of Both RCS Subcooling Monitors. Caused by Deficiency in Installation Procedures.Computer Repaired & Restarted
05000295/LER-1983-031-03, /03L-0:on 830819,while Reviewing MSIV Schematic Drawings,Continuity of Keane Solenoid Valve Coil & Hfa Operate Relay Coil Could Not Be Verified Using Existing Test Procedure.Procedure Change Initiated
05000281/LER-1976-013-03, /03L:on 760820,outside Isolation Valve 2-SI-73 in Accumulator Test Line Found Open.Caused by Inadequate Implementation of Administrative Controls.Valve Closed
05000281/LER-1976-016-03, /03L:on 761230,boron Injection Tank (Bit) Concentration Was 11.4% Weight.Caused by Leakage Through Bit Inlet Valves MOV-2867A & B.Boric Acid Batched to Storage Tank C Concentration to 11.9%
05000281/LER-1976-012-03, /03L:on 760813,routine Sample of Safety Injection Accumulator C Indicated 1,893 Ppm Boron.Caused by Leaking Check Valves 2-SI-147 & 2-SI-145.During Refueling,Check Valves Will Be Inspected & Repaired
05000280/LER-1976-001-01, /01T:on 760302,discovered Process Vent Air Particulate Monitor Isolated.Caused by Technician Error. Monitor Returned to Svc & Technician Instructed to Ensure Full Operability
05000281/LER-1976-009-99, /99T:on 760204,main Steam Line Trip Valve TV-MS-201A Failed to Closed When Operated from Control Room. Caused by Valve Disc Binding Against Valve Body.Disc Opening Adjusted
05000281/LER-1976-002-01, /01T:on 760511,small Cracks & Radial Growth Observed on Periphery of Seventh Tube Support Plate.Caused by Change from Phosphate to Avt Chemistry.Further Investigation in Progress
05000281/LER-1976-003-03, /03L:on 760412,condenser Outlet Valve MOV-CW-200A Would Not Operate.Caused by Water in Limit Switch Compartment & Motor.Motor & Limit Switch Repaired & Limit Switch Compartment water-proofed
05000281/LER-1976-003-01, /01T:on 760521,routine Chemistry Analysis of Primary Coolant Boron Concentration Indicated Unplanned Dilution Occurred.Caused by Three Tubes Out on Steam Generator 2A.Tubes Plugged
05000280/LER-1976-003-03, /03L:on 760326,ruptured Diaphragm in Valve 1-CH-85 Caused Exccessive Leakage of Borated Water.Caused by Normal Wear.Power Rampdown Commenced,Valve Repaired & Placed Back in Svc
05000281/LER-1976-008-03, /03L:on 760614,condenser Outlet Valve MOV-CW-200B Would Not Operate Electrically.Caused by Broken Off Valve Operator Worm Shaft Tripper Cam.Tripper Cam Replaced & Valve Tested & Returned to Svc
05000280/LER-1976-002-03, /03L:on 760318,auxiliary Feedpump Discharge Valve MOV-FW-151A Failed to Open When Main Feedpump Breakers Opened.Caused by Timing Relay Plunger Failure to Activate Micro Switch.Timing Relay & Switch Replaced
05000281/LER-1976-002-03, /03L:on 760409,trip Valve TV-SS-201A Failed to Close When Operator Attempted to Close Valve from Control Panel.Vendor Contacted to Determine Cause.Valve Tested Satisfactorily W/O Prior Maint Activity
05000280/LER-1976-005-01, /01T:on 760805,NSSS Vendor Informed of Error Discovered in LOCA ECCS Analysis.Reactor Vessel Upper Head Water Temp Should Be Assigned Value Similiar to Hot Leg Temp
05000281/LER-1976-005-01, /01T:on 760915,pressurizer Level Fell 45% Below Level Set Point.Caused by Tube Leak in Steam Generator A. Steam Generator Isolated
05000281/LER-1976-004-01, /01T:on 760606,after Maint on Valve 1-CH-125,heat Tracing Circuits on Boric Acid Tank C Recirculation Line Not Placed Back Into Operation.Operating Procedure 1D Modified
05000280/LER-1976-008-03, /03L:on 760702,safety Injection Accumulator B Indicated 1,928 Ppm Boron.Caused by Leaking Check Valves 1-SI-128 & 1-SI-130.Accumulator Recirculated in Raw Water Storage Tank to Increase Boron Concentration
05000280/LER-1976-008-01, /01T:on 761007,broken Stud from Steam Generator 2A Girth Strap Discovered.Caused by Degradation of Stud Coating & High Stresses Developed During Mfg.Studs Replaced.Addl Rept Encl
05000280/LER-1977-001-03, /03L:on 761113,pressurizer Safety Valve Setpoints for Valves SV-1551A & SV-1551B Found Below 2,485 Psig Requirement.Caused by Setpoint Drift.Testing Procedure Will Be Revised
05000280/LER-1977-006-03, /03L:on 770208,charging Pump Cooling Water Pump 1-CC-P-2A Tripped Due to Thermal Overload.Caused by Faulty Motor Bearings.Bearings Replaced & Minor Mechanical Defects Corrected
05000281/LER-1976-004-03, /03L:on 760422,valve MOV-SW-202B Failed to Close When Cls Hi-Hi,Train B Signal Actuated During Testing.Caused by Corroded Contacts on Torque Switch.New Torque Switch Installed
05000280/LER-1977-004-03, /03L,on 770126,reactor Exceeded 90% Power Hold Point Prior to Recalibr of ex-core Symmetrical Offset Detector Sys to in-core Instrumentation Sys.Caused by Personnel Error.Power Reduced
05000280/LER-1976-004-01, /01T:on 760723,indicated Axial Flux Difference Found Outside +6% to -9% Band.Caused by Computer Using Delta I Target Value of -2.0% Instead of 6.5%.Value of Delta I Brought within Correct Target Band
05000280/LER-1977-005-03, /03L:on 770126,when Recirculation to Boron Injection Tank Halted to Repair Leaking diaphragms,150 Mwe/H Rampdown Initiated.Caused by Faulty Diaphragm Matl.Valves Will Be Replaced Periodically
05000281/LER-1977-001-03, /03L:on 770118,recirculation Flow from Boric Acid Tank B Ceased.Caused by Broken Coupling Between Motor & Pump on Transfer Pump 1-CH-P-20.Coupling Repaired
05000280/LER-1976-007-04, /04T:on 760913,during Recalculations of Previous 12 Months,Gaseous & Airborne Particulate Release,Monthly Average,Figured at 0.188% Higher than Limit.Caused by Procedural Errors
05000280/LER-1977-008-03, /03L:on 770220,when Recirculation Halted to Replace Leaking Diaphragm in Valves 1-CH-98,150 Mwe/H Rampdown Initiated.Draphragm Failure Caused by Valve Overtightening When Shutting
05000281/LER-1976-005-03, /03L:on 760427,overall Integrated Containment Leakage Rate Found Greater than Acceptable Criterion.Cause Under Investigation.Repairs Will Be Made Per Investigation Results
05000280/LER-1976-004-03, /03L:on 760416,during Start Test,Emergency Diesel Generator 1 Damaged Due to Flooded Piston Cylinder 17. Caused by Crack in Cylinder Head.Engine Repaired
05000280/LER-1977-007-03, /03L:on 770215,safety Valve SV-MS-101A Lifted Prematurely at Approx 950 Psi,Below Normal Setpoint of 1,085 Psi.Caused by Torque Limiting Device Setting Low Causing Drift.Safety Valves Reset
05000281/LER-1977-003-03, /03L:on 770209,loop C Cold Protection Channel T-432 Failed.Caused by Malfunction of Span Potentiometer in Low Level Amplifier TM-2-432.Amplifier Replaced W/Shop Spare
05000280/LER-1977-009-03, /03L:on 770219,chemical Addition Tank Discharge Valve MOV-CS-102A Position Indicating Lights Extinguished. Caused by Incorrectly Wired Switch.Maint Procedure Revised
05000281/LER-1977-002-03, /03L:on 770126,ability to Maintain Recirculation Between Boric Acid Tank & Boron Injection Tank Lost.Caused by Obstruction in Line from Tank C to Transfer Pumps. Line Back Flushed
05000280/LER-1977-002-03, /03L:on 770120,valves SV-MS-101B & SV-MS-102B Exceeded Setpoint Limits of 1,085 & 1,095 Psig,Respectively. Caused by Setpoint Drift.Valves Adjusted
05000373/LER-1983-067-03, /03L-0:on 830617,HPCS Testable Check Bypass Valve 1E22-F354 Failed to Close.Caused by Insufficient Spring Tension of Actuator Assembly.Spring Tension to Rack & Gear Assembly Increased & Inservice Test Revised
05000295/LER-1982-005, Forwards LER 82-005/01T-0.Detailed Analysis Encl
05000295/LER-1983-020-03, /03L-0:on 830713,unidentified RCS Leak Rate of Approx 1.6 Gpm Found.Caused by Packing Leakage of 0.8 Gpm of Two Boron Injection Tank Inlet Valves.Work Requests Issued & Leakage Reduced to Less than 1 Gpm
05000295/LER-1983-017-03, While at 78% Power & MSIV Partial Close Test (PT-3D) in Progress,High Steam Flow Safety Injection Occurred & MSIV 1D Found Open.Caused by MSIV Test Switch in Reset Position
05000304/LER-1983-022-03, /03L-0:on 830626,steam Generator 2D Feedwater Flow Channel 2F-531 Observed Tracking Low.Caused by Transmitter 2FT-531 Drifting.Transmitter Replaced W/Spare & Replacement Being Evaluated
05000304/LER-1983-018-03, /03L-0:on 830527 & 29,steam Generator 2D Steam Flow Channel 2F-533 Observed Spiking Erratically.Caused by Electronic Clock Circuitry in Extractor Out of Alignment. Module Replaced
05000304/LER-1983-013-01, /01T-0:on 830512,during Air Pressure Test of One Cooling Bank on 2C Reactor Containment Fan Cooler,Six Leaking Tubes Verified.Caused by Internal Pitting.Two Tubes Removed for Visual & Metallurgical Exam
05000304/LER-1983-014-03, /03L-0:on 830427,during Visual Insp,Snubbers Msrs 150-2,MSRS 150-11 & Sirs 2135 Failed to Lock Up in Tension &/Or Compression.Caused by Hydraulic Fluid Leak Due to Poor Seal Condition
05000304/LER-1980-009, /03L-0 for Zion Re Conditions Leading to Operation in a Degraded Mode Permitted by a Limiting Condition for Operation or Plant Shutdown Required by a Limiting Condition for Operation Requires a 30 Day Written Report
0CAN042401, Radioactive Effluent Release Report for the 2023 Calendar Year
0CAN042301, Radioactive Effluent Release Report for 2022
05000304/LER-1977-080, Forwards LER 77-080/03L-0,reclassified as Reportable on 790109 After Internal Review
05000304/LER-1977-082, Forwards LER 77-082/03L-0,reclassified as Reportable on 790126
05000304/LER-1977-081, Forwards LER 77-081/03L-0,reclassified as Reportable on 790109 After Internal Review
05000280/LER-2076-002, Re Failure to Close of Main Steam Trip Valve, TV-MS-201A
05000280/LER-2076-006, Re Out of Specification High Level Trip Setpoints of Two of Three Pressurizer Level Transmitters
05000280/LER-2076-012, Re Routine Sample of C Safety Injection Accumulator Indication of 1893 Ppm Boron
05000280/LER-2077-001, Re Cease of Recirculation Flow from B Boric Acid Tank
05000280/LER-2076-009, Re Non-Operable MOV-2862B When Cycled by Console Control Switch
05000280/LER-2076-016, Re Low Boron Concentration of 11.4% by Weight in Boron Injection Tank
05000280/LER-2076-003, Re Non-Operable Condenser Outlet Valve
05000280/LER-2076-008, Re Electronically Non-Operable Condenser Outlet Valve MOV-CW-200B
05000280/LER-2077-014-03, L for Surry Unit 2 During Normal Operation, While Attempting Routine Boration to Achieve Proper RCS Concentration, No Flow Through FCV-2113A
05000280/LER-2076-013, Safety Injection Accumulator B Revealed Outside Isolations Valve in Accumulator Test Line Open
05000280/LER-2076-007, Re Refueling Water Chemical Addition Valve MOV-CS-202B
05000280/LER-2077-003, Submit Reportable Occurrence No. RO-S1-77-03 Re Failure of Trip Valves to Close from Control Panel
05000280/LER-2076-002-03, Failure of Auxiliary Feedpump Discharge Valve MOV-FW-151A to Open When Main Feedpump Breakers Were Opened
05000280/LER-2077-019, Submit Reportable Occurrence No. RO-S1-77-19 Re More than One Snubber Inoperable
05000280/LER-2077-004, Submit Reportable Occurrence No. RO-S1-77-04 Re Administrative Error During Power Escalation
05000281/LER-1981-010-03, /03L-0:on 810209,svc Water pump,2-SW-P-10B, Developed Low Discharge Pressure.Caused by Eel Lodged in Impeller.Eel Removed & Pump Returned to Svc
05000280/LER-1980-037-03, While Performing Periodic Test 26.1,radiation Monitor RM-SV-111 Found Inoperative. Caused by Spare Lug Short Causing Erroneous Indications. Lug Removed.Monitor Returned to Svc
05000280/LER-1980-002-01, /01T-0:on 800320,insp of Containment Following Type a Leak Rate Revealed Eight 1/4 Inch Holders Drilled Through Containment Liner.Caused by Improper Interpretation of Procedure During Design Change 78-48.Repair Planned
05000281/LER-1980-046-03, /03L-0:on 801217,breaker Feeding MOV-CW-200C Found Open.Caused by Coat Hung on Operating Arm of Circuit Breaker.Coat Removed
05000280/LER-1979-008-01, /01T-0 on 790323:during Load Study of 480 Volts Ac Emergency Bus,Discovered That an under-power Condition Could Exist for Postulated LOCA with or W/O Loss of Offsite Power. Caused by Design Deficiencies During Const
05000281/LER-1978-039-03, /03L-0 on 781115:during Normal Oper,It Was Noted That B Loop Hot Leg Temp Sensing Element TI-2-422A Was Drifting Low.Caused by Packing Leak Which Reduced Resistance of the Sensing Element
0CAN051702, Units 1 and 2 - Annual Radiological Environmental Operating Report for 2016
0CAN051302, Annual Radiological Environmental Operating Report for 2012
L-89-001, License Amendment Request Revision to Defueled Technical Specifications Bulk Materials Control Program
0CAN042202, Radioactive Effluent Release Report for 2021
0CAN042102, Radioactive Effluent Release Report for 2020
PNP 2015-031, Independent Spent Fuel Storage Installation (ISFSI) Submits 2014 Radiological Environmental Operating Report
05000280/LER-1976-011-03, /03L:on 760823,diaphragm in Valve 1-CH-125 Failed Causing Leakage of Boric Acid.Caused by Normal Operation. Valve Repaired
0CAN052501, Annual Radiological Environmental Operating Report for 2024