Semantic search

This page or action requires JavaScript to work. Please enable JavaScript in your browser or use a browser where it is supported, so that functionality can be provided as requested. For further assistance, please have a look at the noscript help page.

Options | Search Clear all entries |

Condition

Printout selection

Options

Parameters [+]

limit:

The maximum number of results to return

offset:

The offset of the first result

link:

Show values as links

headers:

Display the headers/property names

mainlabel:

The label to give to the main page name

intro:

The text to display before the query results, if there are any

outro:

The text to display after the query results, if there are any

searchlabel:

Text for continuing the search

default:

The text to display if there are no query results

class:

An additional CSS class to set for the table

transpose:

Display table headers vertically and results horizontally

sep:

The separator between results

prefix:

Control display of namespace in printouts

Sort options

Delete

Add sorting condition

ResultCodeDebugExtra

To embed this query inline into a wiki page use the code below.

{{#ask: [[Category:TEXT-SAFETY REPORT]] [[Site::Dresden||Quad Cities]]
 |?Issue date
 |?Title
 |?Topic
 |format=table
 |limit=50
 |offset=0
 |sort=
 |order=asc
 |mainlabel=
 |searchlabel=[Table view]
}}

Results 1 – 50 previous 50 20 50 100 250 500 next 50

JSON CSV RSS RDF

Query log

{
    "query_string": "[[Category:TEXT-SAFETY REPORT]] [[Site::Dresden||Quad Cities]]",
    "query_source": "SMWSQLStore",
    "query_time": "0.4238",
    "from_cache": false
}

	Issue date	Title	Topic
05000000/LER-1950-237, Updated LER 50-237/01L:on 760406,unacceptable Ultrasonic Indication Found on Isolation Condenser safe-end.Caused by Cracks in safe-ends.Cracked safe-end Removed & Sent to Bmcl for Metallographic Analysis	13 July 1976	Updated LER 50-237/01L:on 760406,unacceptable Ultrasonic Indication Found on Isolation Condenser safe-end.Caused by Cracks in safe-ends.Cracked safe-end Removed & Sent to Bmcl for Metallographic Analysis
05000237/LER-1950-237, Updated LER 50-237/75-048:on 751007,through-wall Crack Found in Drywell/Torus Nitrogen Purge Line 1604-18.Addl Mods, Including Temp Controlled Isolation Valve Installation, Delayed Until Proposal Review	10 June 1977	Updated LER 50-237/75-048:on 751007,through-wall Crack Found in Drywell/Torus Nitrogen Purge Line 1604-18.Addl Mods, Including Temp Controlled Isolation Valve Installation, Delayed Until Proposal Review
05000237/LER-1976-053, Updated LER 76-053/01T-1:on 760803,util Advised by GE That MAPLHGR Limits in Effect No Longer Considered Sufficiently Conservative at Low Core Flow Rates.Problem Thought to Be ECCS Models Used to Determine Rates	3 January 1977	Updated LER 76-053/01T-1:on 760803,util Advised by GE That MAPLHGR Limits in Effect No Longer Considered Sufficiently Conservative at Low Core Flow Rates.Problem Thought to Be ECCS Models Used to Determine Rates
05000237/LER-1976-063, Updated LER 76-063/03L-l:on 761003,stack Gas Sample Pump Flow Appeared Abnormally Low.Caused by Collection of Carbon Impeller Vane Products in Pump Cavity & Filter.Pump & Filter Replaced	3 March 1977	Updated LER 76-063/03L-l:on 761003,stack Gas Sample Pump Flow Appeared Abnormally Low.Caused by Collection of Carbon Impeller Vane Products in Pump Cavity & Filter.Pump & Filter Replaced
05000237/LER-1976-066, Updated LER 76-066/01T-1:on 761113,during Maint Outage,Hpci Injection Valve M02-23018 Found in Closed Position W/Valve Stem Severed.Caused by Mechanical Overstress of Stem.Stem Replaced	13 May 1977	Updated LER 76-066/01T-1:on 761113,during Maint Outage,Hpci Injection Valve M02-23018 Found in Closed Position W/Valve Stem Severed.Caused by Mechanical Overstress of Stem.Stem Replaced
05000237/LER-1982-023, Revised Deviation Rept for LER 82-023/03L-0:on 820623, Wrong Assumption Made for Drywell to Torus Differential Pressure.Caused by High Torus Pressure Transmitter 2-1673 Measurement	23 July 1982	Revised Deviation Rept for LER 82-023/03L-0:on 820623, Wrong Assumption Made for Drywell to Torus Differential Pressure.Caused by High Torus Pressure Transmitter 2-1673 Measurement
05000237/LER-1983-080, Supplemental LER 83-080/03X-1:on 831124,offgas Log Rad Monitor 2-1705-A Delivered Offgas High Alarm & High Alarm Spiked & Drifted Downscale.Caused by Burned Out Resistor. Power Supply Installed & Monitor Calibr	20 December 1983	Supplemental LER 83-080/03X-1:on 831124,offgas Log Rad Monitor 2-1705-A Delivered Offgas High Alarm & High Alarm Spiked & Drifted Downscale.Caused by Burned Out Resistor. Power Supply Installed & Monitor Calibr
05000237/LER-1983-084, Updated LER 83-084/03X-1:on 831230,during Normal Operation, Primary Containment Oxygen Sample from Torus Alarmed on Low Level Sample Flow.Caused by Sample Line Moisture.Line Drained & Leads reconnected.W/840314 Ltr	14 March 1984	Updated LER 83-084/03X-1:on 831230,during Normal Operation, Primary Containment Oxygen Sample from Torus Alarmed on Low Level Sample Flow.Caused by Sample Line Moisture.Line Drained & Leads reconnected.W/840314 Ltr
05000254/LER-1976-002, Updated LER 76-002/03L Re Excessive Leakage from Double Gasketed Seal X-4.Initially Reported on 760202.Caused by Equipment Failure & Insufficient Compression.Hatch Bolts Tightened	3 March 1976	Updated LER 76-002/03L Re Excessive Leakage from Double Gasketed Seal X-4.Initially Reported on 760202.Caused by Equipment Failure & Insufficient Compression.Hatch Bolts Tightened
05000254/LER-1982-022, Supplemental LER 82-022/03L-1:on 820816,maint Outage for 1/2B Diesel Fire Pump Exceeded 7-day Limit.Cause Not Stated. Diesel Pump Wear Rings Replaced	7 October 1982	Supplemental LER 82-022/03L-1:on 820816,maint Outage for 1/2B Diesel Fire Pump Exceeded 7-day Limit.Cause Not Stated. Diesel Pump Wear Rings Replaced
05000254/LER-1984-018, :on 840922 & 24,reactor Bldg Fuel Pool Channel B Area Radiation Monitor 1705-16B Spiked High, Tripping Ventilation.Cause Unknown.Corrective Actions for Both Events Will Be Documented in Suppl to LER 84-018	11 October 1984	on 840922 & 24,reactor Bldg Fuel Pool Channel B Area Radiation Monitor 1705-16B Spiked High, Tripping Ventilation.Cause Unknown.Corrective Actions for Both Events Will Be Documented in Suppl to LER 84-018
05000254/LER-1988-001, Sanitized Version of LER 88-001-00:on 880114,records Review Found Two Apparent Overexposures of Contractor Personnel During Fourth Quarter 1980.Caused by Inaccurate Secondary &/ or Primary Dosimetry.Dosimetry Sys Upgraded	28 January 1988	Sanitized Version of LER 88-001-00:on 880114,records Review Found Two Apparent Overexposures of Contractor Personnel During Fourth Quarter 1980.Caused by Inaccurate Secondary &/ or Primary Dosimetry.Dosimetry Sys Upgraded
05000254/LER-1990-013	24 July 1990	LER 90-013-00:on 900626,annunciators on Both Units & Reactor Recirculation Loop Sample Valve Closed.Caused by Actuation of Primary Containment Isolation Valve When Lightning Struck 345 Kv Line.Valve reopened.W/900724 Ltr
05000254/LER-1993-008	11 August 1993	LER 93-008-00:on 930709,reactor Bldg Ventilation Radiation Monitor Setpoints Set non-conservatively Four Times in Five Yrs.Caused by Instrument Maint Program Error. New Computer Program developed.W/930805 Ltr	Offsite Dose Calculation Manual
05000254/LER-1993-009	13 August 1993	LER 93-009-00:on 930714,SBGT Methyl Iodide Test Failed Due to Age of Charcoal Combined W/Stringent Test Criteria. Replaced Charcoal Absorber in Both Trains of Sbgt. W/930806 Ltr
05000254/LER-1993-010	19 August 1993	LER 93-010-00:on 930720,HPCI Declared Inoperable & HPCI Outage Rept Qcos 2300-2 Initiated Because IST Flow Rate Fell in IST Required Action Range Due to New Procedure. Surveillance Procedure Will Be revised.W/930819 Ltr
05000254/LER-1993-011	18 August 1993	LER 93-011-00:on 930721,discovered That 4kV Breaker 68 Feeding CS 1B Motor Pump Open & Discharged,Resulting in CS 1B Being Declared Inoperable.Wr Written to Investigate & repair.W/930813 Ltr
05000254/LER-1993-012	24 August 1993	LER 93-012-00:on 930726,light Socket Shorted Out When Operator Reset HPCI Logic Power.Caused by Short Circuit in Light Socket.Light Socket & Blown Fuses replaced.W/930824 Ltr	Reactor Vessel Water Level
05000254/LER-1993-013	27 August 1993	LER 93-013-00:on 930729,identified Deviation from TS & Reg Guide 1.52 Requirements for Methyl Iodide Testing of Charcoal Sample Canisters.Caused by Failure to Implement Proper Canister Testing.Canisters Tested by Nucon
05000265/LER-1976-012, Updated LER 76-012/03L-1 Correcting Event Type,Category & Rept type.W/761001 Forwarding Ltr	1 October 1976	Updated LER 76-012/03L-1 Correcting Event Type,Category & Rept type.W/761001 Forwarding Ltr
05000265/LER-1982-018, Supplemental LER 82-018/03L-1:on 821006,emergency Diesel Generator Tripped on High Temp After Loading.Caused by Fouling of Diesel Generator Cooling Water Sys.Both HX Replaced	1 December 1982	Supplemental LER 82-018/03L-1:on 821006,emergency Diesel Generator Tripped on High Temp After Loading.Caused by Fouling of Diesel Generator Cooling Water Sys.Both HX Replaced
05000265/LER-1983-018, Revised LER 83-018/01T-1:on 831011,discovered 1-1/4 Inch long,20% through-wall Linear Indication in Weld 12S-S27. Caused by Intergranular Stress Corrosion Cracking.New Welds & Elbow Installed	2 February 1984	Revised LER 83-018/01T-1:on 831011,discovered 1-1/4 Inch long,20% through-wall Linear Indication in Weld 12S-S27. Caused by Intergranular Stress Corrosion Cracking.New Welds & Elbow Installed	Hydrostatic Liquid penetrant
05000265/LER-1983-020, Revised LER 83-020/01T-1:on 831028,weld 02B-S9,22-inch Pipe to Cap,Weld 02BS-S12,28-inch Elbow to Pipe & Weld 02BS-F14, 28-inch Pipe to Elbow Weld Had Circumferential Linear Indications	9 December 1983	Revised LER 83-020/01T-1:on 831028,weld 02B-S9,22-inch Pipe to Cap,Weld 02BS-S12,28-inch Elbow to Pipe & Weld 02BS-F14, 28-inch Pipe to Elbow Weld Had Circumferential Linear Indications	Weld Overlay
05000265/LER-1983-021, Revised LER 83-021/01T-5:on 831028,ultrasonic Exams of Large Bore Stainless Steel Pipe Welds Identified 11 Welds W/Crack Indications.Caused by Intergranular Stress Corrosion Cracking.Weld Overlay Performed	28 February 1984	Revised LER 83-021/01T-5:on 831028,ultrasonic Exams of Large Bore Stainless Steel Pipe Welds Identified 11 Welds W/Crack Indications.Caused by Intergranular Stress Corrosion Cracking.Weld Overlay Performed	Weld Overlay
05000265/LER-1988-006, Errata to LER 88-006-02:on 880404,station Notified That Eleven Flued Head Anchors Did Not Meet Design Requirements. Caused by Misinterpretation of Scope & Design Structures.Mod Initiated to Revise Structure	4 June 1992	Errata to LER 88-006-02:on 880404,station Notified That Eleven Flued Head Anchors Did Not Meet Design Requirements. Caused by Misinterpretation of Scope & Design Structures.Mod Initiated to Revise Structure
B130172, Safety Evaluation for Quad Cities Unit 1 Core Spray Line Repair	31 January 1996	Safety Evaluation for Quad Cities Unit 1 Core Spray Line Repair	Safe Shutdown Abnormal operational transient Flow Induced Vibration
ML17174A100	30 October 1979	LER 79-055/03L-0:on 791004,following Pipe Hanger Repairs, Valve 2-1601-60 Failed to Close by Moving Control Switch, But Did Close When Versa Air Switching Valve Was Tapped. Caused by Malfunction of Versa Air Switching Valve
ML17174A109	29 October 1979	LER 79-054/03L-0:on 791004,portion of Drywell Ventilating Line 2-1605-10 Declared Inoperable Due to Degraded Pipe Supports.Caused by Insufficient Thread Engagement & Missing Nuts,Causing Hanger Supports to Become Loose.Nuts Replaced
ML17174A111	1 November 1979	LER 79-053/03L-0:on 791003,trip of Fuel Pool Area Radiation Monitor Resulted in Autostart of Standby Gas Treatment Sys & Isolation of Rx Bldg Vent Sys.Caused by Diaphram Drift to Setpoint Shift
ML17174A114	31 October 1979	LER 79-057/01T-0:on 791019,while in Shutdown,Three of 16 MSIV Scram Limit Switches Found W/Setpoints Greater than 10%.Caused by Not Performing Field Calibr on Switch Setpoints Set by Manufacturer.Limit Switches Readjusted
ML17174A117	30 October 1979	LER 79-027/03L-0:on 791003,half of Trip Sys Inoperable Due to Lifting of Flooding Magnetrol Switch Leads to Condenser Pit.Switch Leads Reattached.No Precise Cause Found
ML17174A124	22 October 1979	LER 79-033/03X-1:on 790428,while Performing Primary Containment Isolation Valve surveillance,2CTIP Machine Did Not Retract During Group 2 Isolation Test.Caused by Ball Valve Limit Switches Not Making Up When Ball Valve Opened
ML17187A804	28 February 1994	Containment Analysis of DBA-LOCA to Update Design Basis for Lpci/Ccs, for GENE-637-042-1193
ML17187A805	31 January 1993	Suppl 1 to GENE-770-26-1092, Long Term Containment Response to DBA-LOCA w/65 Fdegrees F Svc Water Temperature,80 Degrees F Initial Pool Temperature & Initiation of Containment Cooling at 1800 Seconds.	Reactor Vessel Water Level Fuel cladding
ML17192A519	14 February 1980	LER 80-002/03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause
ML17193A708	30 November 1980	SEP Review of NRC Safety Topic VI-7.A.3 Associated W/ Electrical,Instrumentation & Control Portions of ECCS Actuation Sys.	Scram Discharge Volume Fuel cladding Coast down
ML17194A063	31 May 1981	Errata & Addenda Sheet 5,replacing Pages V/VI,3-1/3-2,4-10, 4-12,4-13 & 4-14 to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations.
ML17194A065	31 July 1981	Errata & Addenda Sheet 6,replacing Pages V/VI,3-1,3-2,4-3 & 4-14,to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations.
ML17194A372	31 December 1981	Control Room Habitability Study for Quad Cities 1 & 2, Final Rept
ML17195A952	18 September 1985	Safety Evaluation Approving Util plant-unique Analysis Rept on Pool Dynamic Loads
ML17195A953	18 September 1985	Safety Evaluation Approving Util Mods to Containments & Torus Attached Piping as Documented in COM-02-041-1 Through 7 Entitled, Technical Evaluation of Dresden Nuclear Power Station Units 2 & 3,Plant-Unique Analysis Rept.
ML17202G776	31 December 1989	Core Operating Limits Rept,Dresden Station Unit 2,Cycle 12,Rev 0.
ML17202L259	31 May 1990	Rev 1 to Core Operating Limits Rept,Dresden Station Unit 2, Cycle 12.	Fuel cladding
ML17202L288	29 June 1990	II Upper Vessel Contract Variation Review.
ML17252A753	30 November 1992	Lpci/Containment Cooling Sys Evaluation.	Reactor Vessel Water Level Coatings Turbine Missile Flow Induced Vibration
ML17338B327	20 September 1979	LER 79-021/03L-0:on 790821,during Normal Operation,Offgas Monitor 3A Took Step Increase W/No Power Change & hi-hi Trip Light Was On.Caused by Faulty V1 Electrometer Tube,Which Was Replaced.Monitors Will Be Tested Monthly	Power change
ML17338B328	17 September 1979	LER 79-023/03L-0:on 790823,source Range Monitor Calibr Supplied Rod Block Trip at 1.03E5,exceeding Tech Specs Limit.Caused by Drift & Temp Dependency in Source Range Monitor.Defective Component Not Yet Identified
ML17340B416	26 March 1980	Updated LER 80-030/03X-1:on 791110,during Scram Testing in Refuel Mode,Substantial Loss of Position Indication Noted for Control Rod Driveline H-9.Caused by Improperly Seated Socket,Suggesting Faulty Electrical pin-socket Alignment
ML17340B419	28 March 1980	LER 80-011/03L-0:on 800305,while Conducting Steam Line Area Temp Switch Calibr Surveillance,Temp Switch TS 3-261-17B Tripped Above Tech Specs.Caused by Dirt Deposits on Switch Actuation Plunger.Switch Cleaned,Adjusted & Tested
ML17352B250	1 October 1993	LER 93-014-00:on 930902,discovered That IRM 11 & APRM Both in Bypassed Condition W/O Half Scram Being Inserted Due to Work Practices.Irm 11 Taken Out of Bypassed Condition & Individual Involved counselled.W/931001 Ltr	Half scram

Semantic search

Query log

Navigation menu

Search