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Issue date | Title | Topic | |
---|---|---|---|
ML20205K385 | 31 December 1998 | Dow Triga Research Reactor Annual Rept for 1998. with | |
ML20203A103 | 11 February 1998 | Safety Evaluation Supporting Amend 8 to License R-108 | |
ML20217P634 | 31 December 1997 | Dow Triga Research Reactor Annual Rept - 1997 | |
ML20210R122 | 19 August 1997 | Safety Evaluation Supporting Amend 7 to License R-108 | |
ML20137C540 | 31 December 1996 | Dow Triga Research Reactor Annual Rept - 1996 | |
ML20101F276 | 31 December 1995 | Dow Triga Research Reactor Annual Rept - 1995 | |
ML20081F149 | 31 December 1994 | Dow Triga Research Reactor Annual Rept-1994 | |
ML20063G729 | 31 December 1993 | Dow Triga Research Reactor Annual Rept for 1993 | |
ML20127B466 | 31 December 1992 | Dow Triga Research Reactor Annual Rept 1992 | |
ML20141M046 | 31 December 1991 | Dow Triga Research Reactor Annual Rept - 1991 | |
ML20077B473 | 10 May 1991 | Ro:On 910507,operator Failed to Perform Surveillances & Channel Tests for All 6 Scram Channels & 2 Interlocks Prior to Reactor Operation.Caused by Personnel Error. Tailgate Meeting Held & Mods to Hardware Initiated | |
ML20081M756 | 26 March 1991 | Dow Triga Research Reactor Annual Rept - 1991, Covering May - Dec 1990 Period | |
ML20062F749 | 19 November 1990 | Microprocessor-Based I&C Sys for Dow Triga Research Reactor | |
ML20081E090 | 30 June 1990 | Dow Triga Research Reactor Annual Rept - 1990 | |
ML18094B321 | 28 February 1990 | Annual Operating Repts for 1989 for Salem & Hope Creek Generating Stations | |
ML20012A901 | 27 February 1990 | Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp | |
ML20011F597 | 22 February 1990 | Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used | |
ML20011F194 | 22 February 1990 | Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage | |
ML18153C101 | 2 February 1990 | Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl | |
ML17223A745 | 26 January 1990 | Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N | |
ML20006B658 | 19 January 1990 | Ro:On 900116,wide Range Log Channel Failed While Reactor Taken to Power.Caused by Poor Connection in Rotary Switch in Wide Range Log Channel.Authorization to Replace Entire Control Console Initiated in Early Jan 1990 | |
ML20006A823 | 10 January 1990 | Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 | |
ML20005G683 | 5 January 1990 | Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced | |
ML17347B462 | 31 December 1989 | App a to USI A-46 & Generic Ltr 87-02. | Safe Shutdown Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Backfit |
ML19354D587 | 21 December 1989 | Ro:On 891220,wide Range Log Channel Failed While Reactor Was Being Taken to Power.Caused by Poor Connection in Rotary Switch in Log Channel.Switch Repaired & Reactor Returned to Operation | |
ML18094B147 | 25 October 1989 | Emergency Plan Annual Exercise 1989 for Artificial Island on 891025. W/One Oversize Drawing | |
ML19325E086 | 16 October 1989 | Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway | |
ML19351A294 | 9 October 1989 | Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment | |
ML20248G829 | 2 October 1989 | Rev 19 to YOQAP-I-A, Operational QA Program | Boric Acid Probabilistic Risk Assessment Nondestructive Examination Condition Adverse to Quality Liquid penetrant Fire Protection Program |
ML19351A419 | 30 September 1989 | Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. | Boric Acid |
ML19327C068 | 30 September 1989 | Nuclear Safety & Compliance Semiannual Rept Number 11,Apr- Sept 1989. W/891027 Ltr | High Radiation Area Hydrostatic NJPDES |
ML17347B382 | 30 September 1989 | Monthly Operating Repts for Sept 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/891016 Ltr | |
ML20248F000 | 29 September 1989 | Debris in Containment Recirculation Sumps, Technical Review Rept | Boric Acid Foreign Material Exclusion |
ML19325C952 | 29 September 1989 | Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced | |
ML20248D157 | 13 September 1989 | Rev 56 to QA Program | Nondestructive Examination Liquid penetrant |
ML20248E012 | 13 September 1989 | Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating | |
ML20247K253 | 11 September 1989 | Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively | |
ML20247E376 | 7 September 1989 | Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively | Offsite Dose Calculation Manual Process Control Program |
ML17347B334 | 31 August 1989 | Monthly Operating Repts for Aug 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/890913 Ltr | |
ML20246D687 | 14 August 1989 | Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks | |
ML20248C073 | 3 August 1989 | Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants | |
ML18008A031 | 31 July 1989 | NTH-TR-01 Decrease in Heat Removal by Secondary Sys. | Safe Shutdown Rod Drop Event |
ML17347B273 | 31 July 1989 | Monthly Operating Repts for Jul 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2 | |
ML19327B401 | 31 July 1989 | Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. | |
ML20246P711 | 17 July 1989 | Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available | |
ML20247D301 | 12 July 1989 | Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified | |
ML20246D671 | 30 June 1989 | Criticality Analysis of Byron/Braidwood Fresh Fuel Racks | |
ML20247H071 | 30 June 1989 | Description & Verification Summary of Computer Program, Gappipe | Earthquake |
ML17347B274 | 30 June 1989 | Corrected Monthly Operating Repts for June 1989 for Turkey Point Units 3 & 4 | |
ML17347B185 | 30 June 1989 | Monthly Operating Repts for June 1989 for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4.W/890717 Ltr |