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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20024E660 | 4 August 1983 | RO 83-18:on 830804,during Maint Insps on Hydraulic Snubbers, Two Small Bore Snubbers Identified as Being Installed on RCS Hot Leg Vent Piping Downstream of Valves RC-V15A & B.Caused by Personnel Error | |
| ML20050A543 | 18 March 1982 | Ro:On 820318,water W/Ph of 3.5 Was Discharged from Secondary Waste Water Neutralizing Tank WT-T-1 Into Plant Discharge Effluent Stream.Caused by Accidental Overflow of Approx 2,500 Gallons of Water from Neutralizing Tank | |
| ML20039C633 | 23 December 1981 | RO 81-14:nine Pipe Support & Structural Interfacing Areas Identified Requiring Further Evaluation & Potential Corrective Action.Failure of Pipe Supports Could Damage safety-related Components.Followup Rept Expected in 14 Days | |
| ML19345A974 | 17 November 1980 | RO 80-013/03L-0 Committed to Forwarding Final Valve Testing Evaluation by 801101.Investigation Requires More Time than Anticipated.Requests Extension Until 801219 | |
| ML19338F546 | 23 September 1980 | RO 80-17:on 800923,determined That There Is Insufficient Documentation to Demonstrate Environ Qualification of Brakes on Motor Operators for Purge Valves AH-V1B & AH-V1C. Cause Not Stated.Corrective Action Will Be Submitted | |
| ML19337A863 | 23 September 1980 | RO 80-17:determined Insufficient Documentation to Demonstrate That Brakes on Motor Operators for Purge Valves AH-V1B & AH-V1C Environmentally Qualified.Redundant Valves Fully Qualified | |
| ML19330C304 | 4 August 1980 | Ro:On 800716,during Radiation Emergency Exercise,Use of Emergency Notification Sys Phone Line Became Uncertain, Making Accurate Info Transfers Questionable.Recommends That Microphone Headset Be Made Available to Allow Mobility | |
| ML19326E206 | 22 July 1980 | RO 80-15/4P:confirming 800722 Telcon,On 800721,river Water Discharge Temp Was More than 3 F Below Inlet River Water Temp for Approx 6-h.Incident Will Be Reviewed to Determine Corrective Action.Review to Be Included in Followup Rept | |
| ML19326E084 | 27 June 1980 | RO 80-12/IP:during Review of Equipment Required by IE Bulletin 79-01B,found That post-accident Pressure & Temp Would Be Higher than Postulated in NSC 730705 Rept.Short & long-term Action to Be Discussed in Followup Rept | |
| ML19323H342 | 6 June 1980 | RO-80-10/1P:on 800603,B&W Ltr Informed Util of Potential Reportability of Steam Generator Tube Rupture Safety Analysis.Caused by Nonconservative Error in Fsar.Corrective Action Will Be Addressed in Followup Rept | |
| ML19323D515 | 23 April 1980 | RO 80-07/TP:on 800423 Results of Radiographic Exams of Piping Welds Associated W/Reactor Bldg Penetrations 415-16 for Leak Rate Test Sys Showed Several Welds Not within Tech Specs.Unit Is Shut Down | |
| ML19309A783 | 26 March 1980 | RO 80-06/1P:on 800325,during Refueling Frequency Reactor Bldg Local Leak Rate Test of Valve RB-V7,updated Total Leakage Exceeded Tech Specs.Testing Is Continuing W/Approx 1/4 of Test Program Complete | |
| ML19322B508 | 8 November 1979 | RO 79-17/1P:on 791108 Support Boltings for Rigid Anchor DHH-127A Found to Be Inadequate in Design & Installation. Details & Corrective Action Will Be Addressed in Followup Rept | |
| ML19308A524 | 2 February 1978 | RO 78-08/1P:on 780202,util Informed by NSSS of Deviation Discovered Between FSAR Steam Line Break Analysis & Actual Operating Parameters.Procedure Mod Will Limit Secondary Site Water Volume | |
| ML19308A508 | 20 January 1978 | RO 78-05/1P:on 780119,Plant Operations Review Committee Determined That Containment Integrity Had Been Violated by Opening of Valve BS-V47A & B Following Test of BS-P1A & B. Procedure Mod Will Terminate Operation of BS-V-47A & B | |
| ML19308A509 | 17 January 1978 | Confirms Telcon on 780117 Re Excessive Leak Off from 1A Makeup Pump Discharge Isolation Valve MU-V-74A Resulting in Gaseous Release 500 Times in Excess of 10CFR20 Limits for Xe-133 & Xe-135.Valve Back Seated,Isolating Leak Off | |
| ML19308A511 | 12 January 1978 | RO 78-2/1P:on 780112,it Was Recognized That Continuous Fire Watch Was Not Established for 63-h After a Emergency Diesel Room Sprinkler Isolation Valve FS-V-156 Was Closed.Caused by Personnel Error.Fire Watch Established on 780112 | Continuous fire watch Fire Watch |
| ML19261F295 | 6 January 1978 | RO 78-01/1P:on 780106,util Informed by B&W That During Certain Transients,Difference Between out-of-core Detectors & Heat Balance May Exceed 4% of Full Power.Frequency of Heat Balance Checks Increased | |
| ML19261F296 | 19 December 1977 | RO 77-29/1P:on 771216,B&W Informed Met Ed That Volume Per Tech Specs Was Insufficient to Bring Reactor to Cold Shutdown condition.TMI-1 Immediately Increased Volume of Source of Concentrated Boric Acid Solution | Boric Acid |
| ML19268B968 | 19 December 1977 | RO 77-30/1P:on 771216,B&W Informed Met Ed That Software Used to Calculate Incore Imbalance Was in Error,In That Background Correction Was Misapplied as Detector Depletes. Error Will Be Corrected Prior to Cycle 4 Operation | |
| ML19308A513 | 5 December 1977 | RO 77-27/1P:on 771203,technician Unable to Open Outer Door of Reactor Bldg Personnel Air Lock.Caused by Jammed Linkage. Reactor Shut Down During Repair of Door Closing Mechanism | |
| ML19308A516 | 15 November 1977 | RO 77-26/1P:on 771114,quadrant Power Tilt Exceeded +2.66% W/Reactor at 15% Full Power During Power Escalation Following Reactor Trip.Within 4-h,quadrant Power Tilt Not Reduced | |
| ML19261F309 | 5 October 1977 | RO 77-23/1T:on 770920,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Personnel Error.Doors Closed.Forwards LER 77-23/1T | |
| ML19261F312 | 20 September 1977 | RO 77-23/1P:on 770920,containment Integrity Violated When Both Doors in Reactor Bldg Personnel Access Hatch Were Open for Approx 10 Minutes.Caused by Problem W/Door Interlock. Interlock & Door Seals Tested | |
| ML19261F313 | 9 September 1977 | RO 77-22/1T:on 770825,B&W-required Operating Restrictions on Decay Heat Removal Pumps Found Contrary to Description of Pump Operating Capability Per Fsar.Caused by B&W Failure to Perform Safety Evaluation.Corrective Action by 770923.W/LER | |
| ML19308A520 | 26 August 1977 | RO 77-22/1P:confirms 770825 Telcon That as Result of B&W New Decay Heat Pump Operating Limitations,Remedial or Corrective Action Could Be Required to Prevent Unsafe Condition. Procedure Change Initiated to Incorporate New Limitations | |
| ML19261F316 | 12 August 1977 | RO 77-19/3L:on 770713,leak in Miscellaneous Waste Evaporator Feed Tank Immersion Heater Shorted Out Heater & Feed Pump. Caused by Matl Failure in Heater Temp Element.Heater Replaced & Operating Procedure Modified.Forwards LER | |
| ML19261F319 | 9 August 1977 | RO 77-21/1T:on 770726,radiation Monitor RM-A2 Out of Svc & Sample of Reactor Bldg Atmosphere Not Taken within 8-h. Caused by Improper Reassembly Following 770725 Surveillance Test.Monitor Repaired & Sample Taken.Forwards LER | Grab sample |
| ML19210A544 | 5 August 1977 | Followup Rept to 770707 Ltr Re Ro:On 770613,radwaste Shipment Leak Discovered.Caused by Acidic Attack of Mild Steel Container at Locations of Incomplete Coverage W/Internal Corrosion Resistant Coating | |
| ML19261F322 | 27 July 1977 | RO 77-18/31:on 770629,Nuclear Svcs River Water Pump NR-P1C Shaft Failed While Operating,Leading to Operation in Degraded Mode.Caused by Mechanical & Procedural Problems. Pump Overhauled,Preventive Maint Procedures to Be Changed | |
| ML19308A521 | 27 July 1977 | RO 77-21/1P:on 770726,radiation Monitor RM-A2 Out of Svc & Sample of Reactor Bldg Atmosphere Not Taken within 8-h. Caused by Improper Reassembly Following 770725 Surveillance Test.Monitor Repaired & Valid Sample Taken | |
| ML19308A523 | 20 July 1977 | RO 77-20/4P:on 770719,ETS Violated in That Plant River Water Discharge Temp Exceeded Limit of 3 F Below Inlet River Water Temp for 10 Minutes.Caused by Passing Storm Front Which Decreased Ambient Air Temp from 94 to 82 F | |
| ML19308A522 | 20 July 1977 | RO 77-20/4P:on 770619,ETS Violated in That Plant River Water Discharge Temp Exceeded Limit of 3 F Below Inlet River Water Temp.Caused by Passing Storm Front Which Lowered Ambient Air Temp from 94 to 82 F | |
| ML19261F325 | 20 July 1977 | RO 77-17/3L:on 770624,inner Door Seal on Personnel Access Hatch Leaked Excesively,Causing Total Reactor Bldg Local Leakage to Exceed Tech Spec 4.4.1.2.3.Caused by Improper Door Installation Procedures.Forwards LER | |
| ML19261F329 | 7 July 1977 | RO on 770713:Tri-State Motor Transit Co Driver Observed Radwaste Leaking from Container on Truck While at Rest Area. Caused by Pinhole Leak in One Liner.Truck Returned to Station Site | |
| ML19261F330 | 28 June 1977 | RO 77-15/3L:on 770529,one of Two Units of 230/4.16 Kv Auxiliary Transformer de-energized,leading to Operation in Degraded Mode Permitted by Tech Spec 3.7.2.b.Caused by Wiring Error on Current Transformers.Sys Repaired.Ler Encl | |
| ML19261F333 | 20 June 1977 | RO 77-14/3L:on 770524,reactor Bldg Isolation Valve RB-V7 Failed to Close on Engineering Safeguards Test Signal, Leading to Operation in Degraded Mode Permitted by Limiting Condition for Operation Per Tech Spec 3.6.6 | |
| ML19261F336 | 9 June 1977 | RO 77-12/3L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Operability of Redundant Pump.Caused by Personnel Error.Redundant Pump Tested Satisfactorily on 770519.Forwards LER 77-12/03L | |
| ML19261F339 | 7 June 1977 | RO 77-13/4T:on 770523,analysis of Plant River Water Discharge Showed Concentration of 760 Parts Per Million. Caused Either by Slug of High Concentration of Suspended Solids from Filter Sump or by Poor Sample.Forwards LER | |
| ML19322A438 | 10 May 1977 | RO 77-07/1P:on 770510,both Reactor Containment Bldg Emergency Personnel Access Doors Open at Same Time.Caused by Closed Outer Door Mechanism While Door Still Was Open | |
| ML19322A439 | 18 April 1977 | RO 77-04/1P:on 770415,nonconservative Error Found in Safety Analysis to Support Increase in Pressurizer Code Safety Valve Setpoint to 2500 Psig.Caused by Erroneous Assumptions Made for Total Combined Relief Valve Capacity | |
| ML19253B963 | 22 March 1977 | RO 77-02/04T:on 770304,river Water Discharge Temp Exceeded Inlet River Water Temp Limitation by 14 F Per Ets.Caused by Insufficient Procedures,Personnel Error,Abnormal Ambient Conditions & Low River Water Temp.Ler Encl | |
| ML19322A440 | 20 March 1977 | RO 77-05/4P:on 770319,river Water Discharge Temp Differential Change More than 2 Degrees in 1-h.Steps Taken to Reduce Decay Heat Removal Load,Reducing River Water Temp Change | |
| ML19253B962 | 8 March 1977 | RO 77-02/04P:on 770304,river Water Discharge Temp Exceeded Inlet River Water Temp by 14 F,Violating 12 F Limit Per Ets. Caused by Low Inlet Temp & High Ambient Temp.Temp Reduced Below Limit | |
| ML19210A268 | 3 February 1977 | RO 77-1/1P:on 770202,both a & B Diesel Generators Had Conditions Affecting Starting Capabilities in Response to Loss of Offsite Power.Both Problems Caused by Cranking Timer Timing Out Prior to Oil Low Speed Switch Operation | |
| ML19261F177 | 29 December 1976 | RO 76-50/4O:on 761221,radionucleide Surface Water Level Ten Times Background Level.Probable Cause Is Chinese Weapons Test,Since Neither Zr-95 Nor Nb-95 Discharged to River from Station During Nov 1976 | |
| ML19261F188 | 26 December 1976 | RO 76-047/01T:on 761216,sodium Hydroxide Tank Levels Fell Below Required Minimum.Caused by Personnel Misreading Tank Level Data & Technical Analyst Failing to Notice Mistake | |
| ML19261F253 | 20 December 1976 | RO 76-48/4o:on 761208,isotope Level Samples from TMI Environs Ten Times Background Levels.Chinese Weapons Tests Probably Caused Excesses of I-131,Zr-95,Nb-95,Ce-141 & Ru-103 in Sediment Samples from TMI | |
| ML19261F256 | 14 December 1976 | Nonroutine 30 Day Rept 75-03,advising That Heated Post Gap Measurements within Acceptable Values.Test Schedule Change Warranted from Weekly to After Each Startup,Once Full Steam Equilibrium Reached & on Monthly Basis Thereafter | |
| ML19308A481 | 13 December 1976 | RO 76-46/1P:on 761212,boron Concentrations in Borated Water Storage Tank Found Below Required Minimum.Boric Acid Injected to Return Concentration to Necessary Valve.Possibly Caused by Water Leakage from Reactor Coolant Sys | Boric Acid |