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 Issue dateTitleTopic
ML20205K38531 December 1998Dow Triga Research Reactor Annual Rept for 1998. with
ML20203A10311 February 1998Safety Evaluation Supporting Amend 8 to License R-108
ML20217P63431 December 1997Dow Triga Research Reactor Annual Rept - 1997
ML20210R12219 August 1997Safety Evaluation Supporting Amend 7 to License R-108
ML20137C54031 December 1996Dow Triga Research Reactor Annual Rept - 1996
ML20101F27631 December 1995Dow Triga Research Reactor Annual Rept - 1995
ML20081F14931 December 1994Dow Triga Research Reactor Annual Rept-1994
ML20063G72931 December 1993Dow Triga Research Reactor Annual Rept for 1993
ML20127B46631 December 1992Dow Triga Research Reactor Annual Rept 1992
ML20141M04631 December 1991Dow Triga Research Reactor Annual Rept - 1991
ML20077B47310 May 1991Ro: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
ML20081M75626 March 1991Dow Triga Research Reactor Annual Rept - 1991, Covering May - Dec 1990 Period
ML20062F74919 November 1990Microprocessor-Based I&C Sys for Dow Triga Research Reactor
ML20081E09030 June 1990Dow Triga Research Reactor Annual Rept - 1990
ML18094B32128 February 1990Annual Operating Repts for 1989 for Salem & Hope Creek Generating Stations
ML20012A90127 February 1990Suppls 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
ML20011F59722 February 1990Part 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
ML20011F19422 February 1990Part 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
ML18153C1012 February 1990Part 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
ML17223A74526 January 1990Part 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
ML20006B65819 January 1990Ro: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
ML20006A82310 January 1990Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1
ML20005G6835 January 1990Part 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
ML17347B46231 December 1989App a to USI A-46 & Generic Ltr 87-02.Safe Shutdown
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Operating Basis Earthquake
Earthquake
Backfit
ML19354D58721 December 1989Ro: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
ML18094B14725 October 1989Emergency Plan Annual Exercise 1989 for Artificial Island on 891025. W/One Oversize Drawing
ML19325E08616 October 1989Followup 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
ML19351A2949 October 1989Part 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
ML20248G8292 October 1989Rev 19 to YOQAP-I-A, Operational QA ProgramBoric Acid
Probabilistic Risk Assessment
Nondestructive Examination
Condition Adverse to Quality
Liquid penetrant
Fire Protection Program
ML19351A41930 September 1989Mark-BW Reload LOCA Analysis for Catawba & McGuire Units.Boric Acid
ML19327C06830 September 1989Nuclear Safety & Compliance Semiannual Rept Number 11,Apr- Sept 1989. W/891027 LtrHigh Radiation Area
Hydrostatic
NJPDES
ML17347B38230 September 1989Monthly Operating Repts for Sept 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/891016 Ltr
ML20248F00029 September 1989Debris in Containment Recirculation Sumps, Technical Review ReptBoric Acid
Foreign Material Exclusion
ML19325C95229 September 1989Part 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
ML20248D15713 September 1989Rev 56 to QA ProgramNondestructive Examination
Liquid penetrant
ML20248E01213 September 1989Supplemental 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
ML20247K25311 September 1989Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively
ML20247E3767 September 1989Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectivelyOffsite Dose Calculation Manual
Process Control Program
ML17347B33431 August 1989Monthly Operating Repts for Aug 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/890913 Ltr
ML20246D68714 August 1989Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks
ML20248C0733 August 1989Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants
ML18008A03131 July 1989NTH-TR-01 Decrease in Heat Removal by Secondary Sys.Safe Shutdown
Rod Drop Event
ML17347B27331 July 1989Monthly Operating Repts for Jul 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2
ML19327B40131 July 1989Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel.
ML20246P71117 July 1989Part 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
ML20247D30112 July 1989Part 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
ML20246D67130 June 1989Criticality Analysis of Byron/Braidwood Fresh Fuel Racks
ML20247H07130 June 1989Description & Verification Summary of Computer Program, GappipeEarthquake
ML17347B27430 June 1989Corrected Monthly Operating Repts for June 1989 for Turkey Point Units 3 & 4
ML17347B18530 June 1989Monthly Operating Repts for June 1989 for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4.W/890717 Ltr