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A list of all pages that have property "Title" with value "Addendum 2 to Crdr Executive Summary". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20236P012  + (Addendum 1 to Rev 4 to Design Adequacy Procedure DAP-4, Completion of Type C Checklist Suppls)
  • ML20129H627  + (Addendum 1 to Rev 4 to Post-Accident Recovery Cost Study of Lacbwr)
  • ML19270H128  + (Addendum 1 to SAR for HN-100 Series 2 Radwaste Shipping Cask Referencing 10CFR71 Type a Packaging Regulations)
  • ML20033A147  + (Addendum 1 to SER for Model Icpp Krypton Shipping Container)
  • ML20085D052  + (Addendum 1 to Safeguards Rept for Phase 1 of Saxton Nuclear Experimental Corp 5-Yr R&D Program)
  • ML19247A999  + (Addendum 1 to Semi-Annual Effluent Release Rept 78-2, Jul-Dec 1978)
  • ML13317A214  + (Addendum 1 to Spec for Concrete Block Masonry at San Onofre Nuclear Generating Station,Unit 1)
  • ML20077N064  + (Addendum 1 to Static Load Test & Sesmic Qualification of Clow Wafer Stop Valve Assemblies)
  • ML20217K624  + (Addendum 1 to Subagreement 3 Pertaining to State Resident Engineers Between NRC & State of Il)
  • ML20132B838  + (Addendum 1 to Suppl 1 to NUREG-0737,CRDR Summary Rept. Westinghouse Proprietary Class 2 Info Withheld (Ref 10CFR2.790))
  • ML20154J410  + (Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve)
  • ML13333A768  + (Addendum 1 to Supplemental Study Rept on Effects of Piping Sys Break Outside Containment)
  • ML20148A384  + (Addendum 1 to Umtrap Green River,Ut,Grn Calculations - Final Design for Review)
  • ML20070T107  + (Addendum 1 to Verification Testing of Separation Between Class IE & Non-Class IE Power Cable in Raceways for Use in LaSalle Nuclear Generating Station - Units 1 & 2)
  • ML20136D558  + (Addendum 1 to WCAP-10444, Ref Core Rept Vantage 5 Fuel Assembly)
  • NL-04-0654, Addendum 1 to WCAP-12825-NP Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Joseph M. Farley Units 1 and 2 Nuclear Power Plants for the License Renewal Program  + (Addendum 1 to WCAP-12825-NP Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Joseph M. Farley Units 1 and 2 Nuclear Power Plants for the License Renewal Program)
  • ML031610789  + (Addendum 1 to WCAP-15306-NP-A, Addendum 1 to WCAP-15306-NP-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code)
  • ML20154A649  + (Addendum 1 to WCAP-8282, Final Rept - Ice Condenser Full- Scale Section Tests at Waltz Mill Facility)
  • W3P86-0048, Addendum 1 to Waterford Steam Electric Station Unit 3 Startup Rept  + (Addendum 1 to Waterford Steam Electric Station Unit 3 Startup Rept)
  • ML20011D699  + (Addendum 1 to, Sacm Diesel Generator Qualification Rept)
  • ML19323H646  + (Addendum 1, Investigation of Preservice Failure of Midland Reactor Pressure Vessel Anchor Studs, for Bechtel Corp)
  • ML17256A977  + (Addendum 1, Lab Collapse Tests, Revision 0,to Steam Generator Evaluation,Ginna Steam Tube Failure Incident, 820125,RE Ginna Nuclear Power Plant)
  • ML19337B540  + (Addendum 1,Revision 1, Consolidated Design Rept for Fort St Vrain Fuel Shipping Cask)
  • ML20027C193  + (Addendum 2 to 820319 Deficiency Rept Re Inadequately Welded Studs on Embedded Strip Plates.Addendum Provides Info Re Shipment of Embeds (Type II Strip Plates & Crane Rail Plates) & Any Associated Problems)
  • ML20011A261  + (Addendum 2 to Application for Renewal of License)
  • ML20236V358  + (Addendum 2 to Crdr Human Engineering Discrepancy Resolution Rept)
  • ML20205P473  + (Addendum 2 to Engineering Practices & Procedures Manual Section 5.38, Design Verification)
  • ML19323A789  + (Addendum 2 to Environ Assessment for Decontamination of Site Reactor Bldg Atmosphere, Draft Rept for Public Comment)
  • ML20198B087  + (Addendum 2 to Mnps Unit 2 Annual Rept,)
  • A000122, Addendum 2 to Order 82-14 to NPDES Permit CA0001228,revising Order 82-14 to Reflect Change in Max Allowable Sewage Treatment Plant Flow for Facility,Issued to Southern California Edison Co  + (Addendum 2 to Order 82-14 to NPDES Permit CA0001228,revising Order 82-14 to Reflect Change in Max Allowable Sewage Treatment Plant Flow for Facility,Issued to Southern California Edison Co)
  • ML20236Q403  + (Addendum 2 to Physics Methodology for PWR Reload Design)
  • ML13316A512  + (Addendum 2 to Quality/Safety-Related Civil Structural Const Spec for Sphere Encl Project for Southern CA Edison Co SONGS-1. Bill of Matl for Storage Tanks & Related Matl Encl)
  • ML13310A979  + (Addendum 2 to Rept on Soil Backfill Conditions,San Onofre Nuclear Generating Station Unit 1)
  • ML20215J956  + (Addendum 2 to Rev 0 to Design Adequacy Procedure DAP-21, Homogeneous Design Activity Validation & Selection of Specific Items for Review)
  • ML20215J883  + (Addendum 2 to Rev 1 to Design Adequacy Procedure DAP-7, Trending & Generic Implications Evaluations)
  • ML20236N934  + (Addendum 2 to Rev 2 to Design Adequacy Procedure DAP-DI-M-001, Mechanical Discipline Walkdown Instruction)
  • ML20085D382  + (Addendum 2 to Safeguards Rept for Phase I of Saxton Nuclear 5-Yr R&D Program)
  • ML20090J630  + (Addendum 2 to Spec 7220-C-1, Soils Investigation & Testing Requirements. Related Info Encl,Including Bechtel Interofc Memos,Info Re Soils QA Audit, & PA Martinez to CPC Re Removal of Diesel Generator Bldg Surcharge)
  • ML20196E175  + (Addendum 2 to Vol 2 to WCAP-12071, Westinghouse Large-Break LOCA Best Estimate Methodology,Vol 2: Application to Two- Loop PWRs Equipped W/Upper Plenum Injection,Addendum 2: Pbnp Plant Specific Analysis)
  • ML20134H032  + (Addendum 2 to WCAP-9561-NP-A, Addendum to BART-A1:Computer Code for Best Estimate Analysis of Reflood Transients)
  • ML22106A003  + (Addendum 2 to the Supplemental Sampling and Analysis Plan for the Ettp: Reference for the Kairos Hermes CP Application)
  • ML17256A979  + (Addendum 2, Lab Fatigue Testing, Revision 0,to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant)
  • ML20236V353  + (Addendum 3 to Crdr Executive Summary)
  • ML20205B213  + (Addendum 3 to Crdr,Human Engineering Discrepancy Resolution Rept)
  • NMP1L3254, Addendum 3 to EP-AA-1013, Rev. 4 and Addendum 4 to EP-AA-1013, Rev. 3 Re Emergency Classification Technical Bases  + (Addendum 3 to EP-AA-1013, Rev. 4 and Addendum 4 to EP-AA-1013, Rev. 3 Re Emergency Classification Technical Bases)
  • ML20205P428  + (Addendum 3 to Engineering Practices & Procedures Manual Section 5.38, Design Verification)
  • ML20202H248  + (Addendum 3 to Millstone Nuclear Power Station,Unit 2 Annual Rept)
  • ML20206N131  + (Addendum 3 to Millstone Nuclear Power Station Unit 3 Annual Rept, Including Changes Not Provided in)
  • ML17237C076  + (Addendum 3 to NEI 08-09, Revision 6 Dated April 2010 System and Services Acquisition)
  • ML20059E610  + (Addendum 3 to Physics Methodology for PWR Reload Design)
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