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    "query_string": "[[Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER &amp; RO)]] [[Site::Vermont Yankee||05000000]]",
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	Issue date	Title	Topic
ML20086E437	27 June 1974	AO 74-10:on 740626,HPCI Inverter Tripped,Rendering HPCI Sys Inoperable.Cause Not Stated.Inverter Replaced
ML20086E460	3 July 1974	AO 74-09:in 740625,movements of LPCI Loop Break Detection Logic Differential Pressure Indicating Switches 2-129B & 2-129C Found Sticking,Causing Pointer to Log Input Pressure. Caused by Frequent Switch Actuation
ML20086E473	26 June 1974	AO 74-09:on 740625,movements of LPCI Loop Break Detection Logic Differential Pressure Indicating Switches 2-129B & 2-129C Sluggish,Causing Pointer to Lag Input Pressure.Switch 2-129B Replaced & 2-129C Placed in Trip Condition
ML20086E500	13 June 1974	AO 74-08:on 740525,water Discovered in Ventilation Ducting & in Instrument Penetrations at Biological Shield.Caused by Leak on Control Rod Drive Hydraulic Sys Return Line to Reactor Vessel,Due to Stress Corrosion Cracking	Hydrostatic Liquid penetrant
ML20086E576	4 June 1974	AO 74-08:detailed Rept & Analysis Including Appropriate Corrective Measures Taken Re 740526 Incident Will Be Submitted within 20 Days of Occurrence
ML20086E583	28 May 1974	AO 74-08:on 740525,water Leakage Discovered Along Reactor Vessel Wall.Caused by Leak on Control Rod Drive Hydraulic Sys Return Line to Reactor Vessel.Engineering Review & Assessment Underway
ML20086E636	15 May 1974	AO 74-07:on 740509,spike Observed on Plant Stack Gas Recorder,Resulting in Stack Release Peak Greater than Allowed by Tech Specs.Caused by Steam Packing Exhauster Operation
ML20086E639	10 May 1974	AO 74-07:on 740509,spike Observed on Plant Stack Gas Recorder,Resulting in Stack Release Peak Greater than Allowed by Tech Specs.Cause Not Stated
ML20086E652	25 April 1974	AO 74-06:on 740418,both Access Doors to North Entrance to Reactor Bldg Found Partially Open.Caused by Personnel Failing to Verify Closure.Design Adequacy Under Review
ML20086E664	19 April 1974	AO 74-06:on 740418,both Access Doors to North Entrance to Reactor Bldg Found Open.Caused by Personnel Failure to Verify Closure.Methods to Assure Closure Underway
ML20086E677	11 March 1974	AO 74-05:on 740304,LPCI Loop a Valve V10-25A Failed to Open When Control Switch Placed in Open Position.Caused by Burned Out Valve Motor.Motor Replaced
ML20086E696	5 March 1974	AO 74-05:on 740304,LPCI Valve V10-25A Failed to Open When Control Switch Placed in Open Position.Caused by Tripped Motor Breaker & Unusually Warm Motor.Motor Replaced
ML20086E713	1 March 1974	AO 74-04:on 740223,MSIV Rv 2-71B Failed to Open at Required Setpoint.Indirectly Caused by Approved vendor-recommended Mods to Certain Relief Valve Internals.Procedure Revised
ML20086E724	25 February 1974	AO 74-04:on 740223,MSIV Rv 2-71B Failed to Open at Required Setpoint.Cause Under Investigation
ML20086E732	11 February 1974	AO 74-03:on 740204,LPCI Differential Pressure Indicating Switch 2-137B Failed to Indicate Properly Upon Isolation from Normal Sys Pressure W/Bypass Valve Open.Caused by Improper Sensor over-range Stop Setting.Sensors Calibr	Overtravel
ML20086E747	4 February 1974	AO 74-03:on 740204,LPCI Differential Pressure Indicating Switch 2-137B Failed to Indicate Properly Upon Isolation from Normal Sys Pressure W/Bypass Valve Open.Cause Not Stated.Sensor Replaced
ML20086E754	7 February 1974	AO 74-02:on 740131,core Spray Sys Valve CS-11A Failed to Open When Control Switch Placed in Open Position.Caused by burned-out Valve Motor.Motor Replaced
ML20086E763	1 February 1974	AO 74-02:on 740131,core Spray Sys Valve CS-11A Failed to Open When Control Switch Placed in Open Position.Cause Not Stated.Surveillance Testing Completed & Sys Aligned to Standby Mode
ML20086E782	31 January 1974	AO 74-01:on 740124,reactor Scrammed,Resulting from Turbine Trip Causing Automatic Closure of All But One Msiv.Valve 2-80C Failed to Close Due to Failure of Pneumatic Pilot Valve to Actuate.Valve Assembly Returned to Vendor for Insp
ML20086E790	25 January 1974	AO 74-01:on 740124,reactor Scrammed Due to Turbine Trip, Causing Automatic Closure of All But One Msiv.Cause of Valve 2-80C Failure Not Stated
ML20086E813	26 December 1973	AO 73-35:on 731219,MSIV Relay 5A-K3C Failed to Energize During Monthly MSIV Functional Test.Caused by Limit Switch Actuating Arm Being in Wrong Position.Arm Manually Reset
ML20086E826	20 December 1973	AO 75-35:on 731219,MSIV Relay 5A-K3C Failed to Energize During Monthly MSIV Functional Test.Caused by Mispositioned Limit Switch Actuating Arm.Arm Manually Reset
ML20086E835	27 December 1973	AO 73-34:on 731217,station Svc Water Pump a 4-kV Breaker Stationary Auxiliary Switch Assembly Rear Mounting Tie Bolt Found Disengaged from Mounting Plate.Caused by Improper Bolt Tightening During Factory Assembly
ML20086E840	19 December 1973	AO 73-34:on 731217,station Svc Water Pump a 4-kV Breaker Stationary Auxiliary Switch Assembly Rear Mounting Tie Bolt Found Disengaged.Bolt Tightened
ML20086H166	26 January 1973	AO 50-271/72-19:on 721227,internal Fault on Startup Transformer Resulted in Loss of Normal Power Onsite.Caused by Failure of Safety Valve a to Lift.Pilot Valve Internals Will Be Replaced & Replacement Transformers Installed
ML20086H170	28 December 1972	AO 50-271/72-18:on 721222,containment Victoreen Air Monitor Pump Failed.Total RCS Leakage Ascertained Daily Until 721227.Pump Repair Completed & Sys Restored to Full Operation
ML20086H172	28 December 1972	AO 50-271/72-17:on 721222,during Monthly HPCI Pump Surveillance Test,Gasket on Gland Seal Exhaust Condenser Failed.Caused by Overpressurization of Condenser Due to Improper Setting of HPCI PCV23-50.Valve Reset
ML20086H176	22 December 1972	AO 50-271/72-17:on 721222,during Monthly HPCI Pump Surveillance Test,Gasket on Gland Seal Exhaust Condenser Failed.Replacement of Gasket Initiated & Cooler Repaired
ML20086H181	21 December 1972	AO 50-271/72-15:on 721219,during HPCI Sys Surveillance,Hpci Steam Line High Differential Pressure Switch DPIS 23-77 Tripped at 200 Inches of Water.Sensor Immediately Reset & Verified
ML20086H186	20 December 1972	AO 50-271/72-15:on 721219,HPCI Steamline High Differential Pressure Switch DPS 23-77 Tripped at 200 Inches of Water. Sensor Immediately Reset & Verified within Limits
ML20086H190	4 December 1972	AO 50-271/72-14:on 821204,during Core Spray Sys Surveillance,Reactor Pressure Switch Ps 2-3-52B Actuated at Less than 335 Psig.Switch Immediately Reset & Verified
ML20086H212	10 November 1972	AO 50-271/72-13:on 721109,during Sampling of Outside Radwaste Tanks,Total Activity of Tanks Found to Be 7.296 Ci, Exceeding Tech Spec Limit of 0.3 Ci.Caused by High Xenon Content in Water.Tanks Recycled & Restored on 721110
ML20086H222	8 November 1972	AO 50-271/72-10:on 721101,scram Discharge Vol High Water Level Switch Lsh 3-231C Failed to Actuate at Tech Spec Limit of 24 Gallons.Caused by Initial Corrosion within Sys.Float Chamber Flushed & Switch Verified
ML20086H225	2 November 1972	AO 50-271/72-10:on 721101,scram Discharge Vol High Water Level Switch Lsh 3-231C Failed to Actuate on High Water Level.Switch Chamber Immediately Cleaned & Flushed & Switch Verified
ML20086H228	7 November 1972	AO 50-271/72-12:on 721106,offgas Sample Chamber Isolated Intentionally to Permit Replacement of Chamber Flow Metering Valve.Valve Found Leaking.Valve Replaced & Three Fittings & One Union Tightened
ML20086H246	1 November 1972	AO 50-271/72-09:on 721026,two Barton Steam Line Differential Pressure Switches (DPIS 13-83 & 13-84) Failed to Actuate at Required Pressure of 180 Inches.Locking Devices May Be Causing Change.Switches Immediately Reset
ML20086H250	27 October 1972	AO 50-271/72-09:on 721026,two Barton Steam Line Differential Pressure Switches (DPIS 13-83 & 13-84) Actuated at 195 Inches,Exceeding Tech Spec Limit of 180 Inches.Switches Immediately Reset
ML20086H255	25 August 1972	AO 50-271/72-02:on 720801-08,airborne Contamination Levels within Containment Exceeded Average Level.Reactor Containment Required Due to Investigation of All Drywell Pressure Penetration taps.Open-ended Tees Plugged
ML20086H270	26 October 1972	AO 50-271/72-08:on 721020,during Automatic Depressurization Sys B Logic Test,Relief Valve Initiation Time Delay Relay 2E-K5B Failed to Energize in 120 S.Relay Immediately Reset
ML20086H275	20 October 1972	AO 50-271/72-08:on 731020,during Automatic Depressurization Sys B Logic Test,Relief Valve Initiation Time Delay Relay 2E-K5B Energized at 123 S,Exceeding Tech Spec Limit of 120 S.Relay Immediately Reset
ML20086H288	3 October 1972	AO 50-271/72-06:on 720928,steam Line High Differential Pressure Switch DPIS 13-84 Failed to Operate at Required 180 Inches of Water.Caused by Broken Common Lead.Lead Repaired
ML20086H295	29 September 1972	AO 50-271/72-06:on 720928,one Channel of Steam Line High D/P Isolation Failed to Operate at 180 Inches of Water.Caused by Broken Common Lead Between Conduit Fitting & Switch Terminal Board.Lead Repaired
ML20086H300	29 September 1972	Ao:On 720904,two Solenoid Operated Isolatation Valves in Torus Sampling Connection Found Not to Close on Isolation Signal.Caused by Valve Piston Binding.Piston Rings Removed, Valves Cleaned & Reassembled
ML20086H303	17 August 1972	AO 50-271/72-02:on 720801-08,during Investigation of All Drywell Pressure Penetration Caps,Reactor Coolant Temp Exceeded Tech Spec Limit.Caused by open-ended Tees.Tees in Sensing Lines Plugged
ML20086H307	26 September 1972	Ao:On 720803,RCIC Sys Turbine Steam Admission Valve RCIC-131 Failed.Caused by Piece of Metal Lodged on Valve Seat & Burned Out Motor.Metal Removed & Motor Replaced
ML20086H309	22 September 1972	AO 50-271/72-05:on 720921,supply Valve to Offgas Sample Chamber Closed.Caused by Inadvertent Shutting of Valve During Initial Operation of Air Ejector Sys.Procedures Revised to Assign locked-open Valves	Time of Discovery Grab sample
ML20086H321	19 October 1972	AO 50-271/72-07:on 721010,alarm Annunicated in Main Control Room Indicating Leak in Bellows Assembly of Main Steam Relief Valve D.Caused by Residual Moisture Trapped in Tubing.Tubing Drained & Vented
ML20086H324	11 October 1972	AO 50-271/72-07:on 721010,alarm Annunciated in Main Control Room,Indicating Leak in Bellows Assembly of Main Steam Relief Valve D.Vendor Evaluating Problem
ML20086H336	27 September 1972	AO 50-271/72-04:on 720919,alarm Annunciated in Main Control Room Indicating Leak in Bellows of Main Steam Relief Valve. Failure Could Render One Relief Valve Incapable of Relieving Steam Pressure at Tech Spec Setpoint
ML20086H343	22 September 1972	AO 50-271/72-05:on 720921,supply Valve to Offgas Sample Chamber Found Closed.Offgas Activity Measured at 5 Mrm/Hr & Grab Sample of Air Ejectors Showed 145 Uci/S.Review Being Conducted	Grab sample

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