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{{#ask: [[Category:TEST REPORT]] [[Site::Braidwood]]
 |?Issue date
 |?Title
 |?Topic
 |format=table
 |limit=50
 |offset=0
 |sort=
 |order=asc
 |mainlabel=
 |searchlabel=[Table view]
}}

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{
    "query_string": "[[Category:TEST REPORT]] [[Site::Braidwood]]",
    "query_source": "SMWSQLStore",
    "query_time": "0.0407",
    "from_cache": false
}

	Issue date	Title	Topic
ML20024H625	8 March 1991	Reactor Containment Bldg Integrated Leak Rate Test (910202- 0305) Braidwood Unit 1.
ML20064A639	30 June 1990	Startup Test Rept Unit 2 Cycle 2	Shutdown Margin
ML20072E511	12 August 1994	Reactor Containment ILRT Comm Ed Braidwood Nuclear Power Station Unit 1
ML20078Q357	9 February 1995	Reactor Containment Bldg ILRT Braidwood Nuclear Power Generating Station Unit 2,941027-1109
ML20082H124	31 July 1991	Unit 1,Cycle 3 Startup Test Rept, Dtd Jul 1991	Shutdown Margin
ML20086S775	28 July 1995	Table 2-10 Summary of Test Dimensional Measurement Results
ML20092H227	17 January 1992	Reactor Containment Bldg Integrated Leak Rate Test (910912- 1116)	Packing leak
ML20094G745	30 April 1984	Rev 1 to Evaluation of Energy Absorbing Matl for Pipe Whip Restraints
ML20098F544	30 September 1984	Rev 0 to Evaluation of Tests Performed on Energy Absorbing Matl for Pipe Whip Restraints	Finite Element Analysis
ML20100F937	16 November 1995	Reactor Containment Bldg Integrated Leak Rate Test for Braidwood Nuclear Power Generating Station	Packing leak
ML20133N021	27 August 1985	Electrical Cable Separation Verification Testing
ML20137Z827	30 November 1984	Nuclear Component Qualification Test Rept Square D 9025-BCW-45 Thermal Switch	Earthquake
ML20141D987	28 February 1986	Rev 0 to ASME Code Evaluation of Braidwood Unit 2 Nozzle F to Include Effects of Proposed Grindouts
ML20147G243	29 February 1988	Cycle 1 Startup Rept	Boric Acid Flow Induced Vibration
ML20151X135	28 October 1983	Rept of Irradiation & DBA Testing	Boric Acid Coatings
ML20153C747	31 August 1988	Cycle 1 Startup Rept Final Suppl	Boric Acid Flow Induced Vibration Reverse polarity
ML20195G637	31 May 1988	Cycle 1 Startup Rept Suppl	Safe Shutdown Power change Flow Induced Vibration
ML20206U214	2 April 1987	Results of in-place Testing for Control Room Ventilation Recirculation Filter Units
ML20214L066	19 August 1986	Reactor Containment Bldg Integrated Leakage Rate Test for Braidwood Unit 1,Preoperation Test on 860521-29
ML20215D027	7 July 1986	Rev 0 to Test Rept of Results of Pressurizer Control Test	Stroke time Scaffolding
ML20236X869	7 December 1987	Reactor Containment Bldg Integrated Leakage Rate Test: Braidwood Nuclear Station Unit 2 Preoperational Test 870906-11

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