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List of results

• ML23135A190  + (Report, M-6630-00017A, Revision W08, Fire Protection Evaluation for Penetrant Size Exceeding Typical Detail FB-1 Limitation)
• ML23135A189  + (Report, M-6630-00017A, Revision W08, Structural Steel Fireproofing Data)
• ML100250858  + (Report, No. HI-2043321, Rev. 6, Critically Safety Analyses of BWR Fuel Without Credit for Boraflex in the Racks at the Harris Nuclear Power Station)
• ML031060339  + (Report, Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model)
• ML21175A332  + (Report: Concerns Pertaining to Uni-Directional Communications -Not Implemented in Software- from High Safety to Lower Safety Systems and Internal Plant to External Systems Connected to the Internet)
• ML20272A218  + (Report: Degradation and Failure Phenomena of Accident Tolerant Fuel Concepts, Fecral Alloy Cladding)
• ML061380558  + (Report: Exceeding NPDES Temperature Permit Limits. Discharge Monitoring Report for March 2006 Also Enclosed)
• ML19050A074  + (Report: Preparations for Efficient and Effective Licensing of Accident Tolerant Fuel Designs (Enclosure))
• ML24198A196  + (Report: Procedure for the Computational Models Created for the Doe/Nrc Collaboration for Criticality Safety Support for Commercial-Scale HALEU Fuel Cycles and Transportation (Dncsh) Project)
• ML050870112  + (Report: Unplanned Isolation of Spent Fuel Cooling (CAP056010))
• ML20235U422  + (Reportability Analysis for 10CFR50.50 to Rev 5 to Engineering Procedure 3.3, Station Safety Evaluations. Related Info Encl)
• 05000237/FIN-2008005-03  + (Reportability for Inadvertent Rod Withdrawal)
• ML023360069  + (Reportable Condition Stability Option III: Period Based Algorithm T Specification)
• ENS 41396  + (Reportable Defect in Sis Control Wire)
• ML18283B369  + (Reportable Deficiency - Possibility of Marginally Adequate Support Structure on Main Steam and Relief Valve Discharge Piping)
• ML18283B375  + (Reportable Deficiency - RPV Stabilizer Plates Installed Incorrectly - IE Control No. H0 1340 F2)
• ML18283B374  + (Reportable Deficiency - RPV Stabilizer Plates Installed Incorrectly - IE Control No. H0 1340 F2)
• ML18283B380  + (Reportable Deficiency - RPV Stabilizer Plated Installed Incorrectly)
• ML17272A398  + (Reportable Deficiency on 781017:defective Terminals Found on Westinghouse-supplied Electrical Penetrations X105 A,B,C & D.Defect Consisted of Wrong Size Lugs Resulting in Loose Connections.Incorrect Size Lugs Removed & Replaced)
• ML17272A532  + (Reportable Deficiency on 790621:emergency Dc Motor Control Ctr Cooler RRA-FC-12 Is Powered from Noncritical Motor Control Ctr MC-7C-A.Design Directive Issued & Power to RRA-FC-12 Is Presently Being Provided)
• ML20125A719  + (Reportable Deficiency:Improper Installation of Anchor Bolts by Waldinger Corp,Contrary to Approved Drawings.Engineering Change Order,Requiring That Anchor Bolts Be Removed & Corrected,Has Been Issued to Contractor)
• ML17272A527  + (Reportable Deficiency:Improper Installation of Concrete Anchors Could Result in Possible Failure of safety-related Equipment During Operation.Contracts Reviewed & Engineering Change Orders Issued)
• ML20195K317  + (Reportable Event 10646:on 871109,discovered That Low Level Radioactive Sheets of Metal Removed from Site & Delivered to Coffee County Landfill.All But Three Pieces Recovered.Search for Remaining Pieces Continuing)
• ML20195K328  + (Reportable Event 10691:on 871116,trash Bag Containing Low Level Contamination Found During Survey of Coffee County Landfill as Followup to Reportable Event 10646.Contaminated Rag Returned to Plant.Survey Continuing)
• ML091170048  + (Reportable Event 44991; Violation of Limiting Conditions of Operation in Technical Specification 3.5B)

• ML101550535  + (Reportable Event Plant Specific: TMI-02)

• ML100700492  + (Reportable Event Rad 1.34, Rev. 10)
• ML100700493  + (Reportable Event Rad 1.4, Rev. 10)
• ML100700507  + (Reportable Event Rad 2.1, Rev. 9)
• ML20029A454  + (Reportable Event Repts Maanshan Nuclear Power Plant)
• NRC-95-0020, Reportable Event That Occurred on 950211.Listed Commitments Made in Ler,Including Clarification of Procedure Requirements to Distinguish Between Use of Test Equipment & Actual Acquisition  + (Reportable Event That Occurred on 950211.Listed Commitments Made in Ler,Including Clarification of Procedure Requirements to Distinguish Between Use of Test Equipment & Actual Acquisition)
• ML19263C963  + (Reportable Event on 790227:feedwater Pipe Whip Restraint Was Installed Incorrectly on Line A.Condition Should Not Cause Damage to Drywell Liner.Measures for a Permanent Solution Are Being Investigated)
• Information Notice 2009-17, Reportable Events Involving Treatment Delivery Errors Caused by the Use of Differing Units for the Calibration of Brachytherapy Sources  + (Reportable Events Involving Treatment Delivery Errors Caused by the Use of Differing Units for the Calibration of Brachytherapy Sources)
• ENS 42144  + (Reportable Incident Due to Deviation from Technical Specification Requirements)
• Information Notice 2007-03, Reportable Medical Events Involving Patients Receiving Dosages of Sodium Iodide Iodine-131 Less than the Prescribed Dosage Because of Capsules Remaining in Vials After Administration  + (Reportable Medical Events Involving Patients Receiving Dosages of Sodium Iodide Iodine-131 Less than the Prescribed Dosage Because of Capsules Remaining in Vials After Administration)
• Information Notice 2007-03, Reportable Medical Events Involving Patients Receiving Dosages of Sodium Iodide Iodine-131 Less Than the Prescribed Dosage Because of Capsules Remaining in Vials After Administration  + (Reportable Medical Events Involving Patients Receiving Dosages of Sodium Iodide Iodine-131 Less Than the Prescribed Dosage Because of Capsules Remaining in Vials After Administration)
• ENS 55739  + (Reportable Occurance Related to Building Exhaust Fan)
• ML031970382  + (Reportable Occurence 50-20/2003-1, Violation of Technical Specification No. 7.2.1)
• ML20064E461  + (Reportable Occurence 78-058/04P on 781105-08:during Plant Shutdown,Reactor Plant River Water & Turbine Plant River Water Header Chlorination Levels Exceeded Allowable Value, Due to Abnormal Lineup)
• ML20064J134  + (Reportable Occurence Rept 50-219/78/28-1P on 781129:Main Steam Line Drain Valve & TIP Isolation Valve for TIPs 1-1 & 1-3 Failed to close.6K27 Relay Replaced,Main Steam Drain Valve Repaired & TIP Sys Switches & Logic Adjusted)
• ML20064J048  + (Reportable Occurence Rept 50-219/78/29-1p:on 781129, Containment Leakage Rate Was Greater than Allowable Caused by Failure of Isolation Condenser Vent Valves,Drywell Vent Valves & DPS66A Switches.Valves Repaired & Replaced)
• ML20035D090  + (Reportable Occurrence 17:on 930324,during Startup & Escalation to Full Power,Discrepancy Noted in Actual Thermal Power.Operating Procedure Modified to Require That Automatic Control Sys Setpoint Be Adjusted to 1 Mv)
• ML19276D931  + (Reportable Occurrence 2-79-1/1P on 790104:review of Safeguard Cable Routing Identified 8 Cables Improperly Designated as non-safeguard Cables.Caused by Improper Designation of Cables During Design Phase)
• ML19276D930  + (Reportable Occurrence 2-79-2/1P on 790108:cable Spread Room Cardox Sys Disabled & No Fire Watch Posted for 51/2 Hours. Caused by Personnel Error)
• ML20064E050  + (Reportable Occurrence 3-78-20/1P on 781019:while Unit 2 Was Being Inerted,Unit 3 Drywell Oxygen Concentration Exceeded Tech Spec Limit by 0.1%.Drywell Was Depressurized & Purged to Bring Oxygen Concentration W/In Limit)
• ML19276D927  + (Reportable Occurrence 3-79-2-1P on 790108: Gaseous Release Rate Exceeded Allowable Tech Spec Limits for Instantaneous Release Rate.Caused by Failure to Maintain Reactor Coolant Temp Sufficiently Low to Prevent Vaporization During Maint)
• ML17266A022  + (Reportable Occurrence 335-B-78-08 on 781117:condenser Temp Rise Exceeded 24 F,Caused by Circulating Water Sys Fouling, But Discharge Canal Temp Did Not Exceed 111 F Degrees)
• ML20078S224  + (Reportable Occurrence 50-020/95-01:on 950206,voltage & Specific Gravity Measurements of Cell of Emergency Battery Bank Recorded at Less than Specified Weekly SR in TS 4.3.5. C/A Will Modify SR to Monthly)
• ML051750408  + (Reportable Occurrence 50-20/2005-1, Missed Daily Secondary Coolant Sample)
• ML18026A626  + (Reportable Occurrence 50-20/2018-1: Operation with Fewer than the Required Number of <100 Kw Nuclear Safety System Level Channel Set to Alarm; NRC OPS Center Log EN 52157)
• ML19269B831  + (Reportable Occurrence 50-20/79-01 on 781226-30:reactor Operated from 781226-30 W/Nuclear Safety Sys Settings for 1 & Possibly 2 of 3 Neutron Flux Level Scrams in Excess of Limiting Safety Sys Settings)