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A list of all pages that have property "Title" with value "Forwards Revision 1 to Security Plan.Revision Withheld". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML19241B277  + (Forwards Revision 1 to Rept on Reanalysis of Safety-Related Piping Sys. Seven Piping Supports Will Be Modified & Two New Supports Will Be Installed.Requests Authorization to Begin Interim Operation Until Refueling)
  • ML19241B278  + (Forwards Revision 1 to Rept on Reanalysis of Safety-Related Piping Sys. Seven Piping Supports Will Be Modified & Two New Supports Will Be Installed.Requests Authorization to Begin Interim Operation Until Refueling)
  • ML20031C525  + (Forwards Revision 1 to Requalification Action Plan, Qualification by Test of Class IE Equipment Per NUREG-0588 & La Salle County Station Assessment to Justify Interim Operation. Suppl to Assessment Being Developed)
  • ML19345G080  + (Forwards Revision 1 to Response Re IE Bulletin 79-14 Revision 1,Suppl 2, Seismic Analysis for As-Built Safety-Related Piping Sys. Describes Program Which Will Give Assurance That Design Documents Reflect Sys Conditions)
  • A810002, Forwards Revision 1 to Response to IE Bulletin 79-01B, Environ Qualification of Class IE Equipment. Revision Addresses Resolution of Outstanding Issues & Other NRC Concerns & Deletes Unnecessary Equipment from Master List  + (Forwards Revision 1 to Response to IE Bulletin 79-01B, Environ Qualification of Class IE Equipment. Revision Addresses Resolution of Outstanding Issues & Other NRC Concerns & Deletes Unnecessary Equipment from Master List)
  • ML19345E582  + (Forwards Revision 1 to SAR for Chem-Nuclear Sys,Inc SGC-1, Type a Radwaste Shipping Cask, in Response to NRC 801212 Request for Addl Info in Support of 800722 Application for Approval of Model SGC-1 Packaging)
  • ML19282D167  + (Forwards Revision 1 to SAR of TN-12 Packaging,In Response to 780907 Request for Addl Info)
  • ML13330A263  + (Forwards Revision 1 to SE-SP-58(80) (Nonproprietary Version) & SE-SP-40(80) (Proprietary Version), Steam Generator Repair Rept. Proprietary Version Withheld (Ref 10CFR2.790). Affidavit & Application for Withholding Encl)
  • ML17193A575  + (Forwards Revision 1 to SEP Review of Safe Shutdown Sys for Dresden Unit 2 Nuclear Power Plant. Requests Notification within 90 Days of Receipt of Ltr If as-built Facility Differs from Licensing Basis)
  • ML19345A919  + (Forwards Revision 1 to SL-3753, Evaluation of In-Place Concrete, Vols I & II)
  • ML19338E990  + (Forwards Revision 1 to Safe Shutdown Analysis for Fires in Control Room,Relay Room or Cable Spreading Rooms, in Response to Question 1 of NRC 800201 Fire Protection Evaluation)
  • ML19338E991  + (Forwards Revision 1 to Safe Shutdown Analysis for Fires in Control Room,Relay Room or Cable Spreading Rooms, in Response to Question 1 of NRC 800201 Fire Protection Evaluation)
  • ML20041E394  + (Forwards Revision 1 to Safeguards Contingency Plan.Revision Withheld (Ref 10CFR73.21))
  • ML19257A252  + (Forwards Revision 1 to Safeguards Contingency Plan Per 791120 Request.Plan Withheld (Ref 10CFR2.790))
  • ML20003A012  + (Forwards Revision 1 to Safeguards Contingency Plan.Plan Withheld (Ref 10CFR2.790))
  • ML19305C241  + (Forwards Revision 1 to Safeguards Contingency Plan.Plan Withheld (Ref 10CFR2.790))
  • ML19323G929  + (Forwards Revision 1 to Safeguards Contingency Plan.Plan Withheld (Ref 10CFR2.790))
  • ML18087A599  + (Forwards Revision 1 to Safety Evaluation of PSEG Rod Exchange Methodology, for Info)
  • ML18087A600  + (Forwards Revision 1 to Safety Evaluation of PSEG Rod Exchange Methodology, for Info)
  • ML19309F021  + (Forwards Revision 1 to Section 3.0 of WCAP-9402, Verification Testing & Analyses of Westinghouse 17x17 Optimized Fuel Assembly. Application for Withholding & Affidavit Encl.Proprietary Version Withheld(Ref 10CFR2.790))
  • ML20010G658  + (Forwards Revision 1 to Security Force Training & Qualification Plan.Revision Withheld (Ref 10CFR2.790))
  • ML13302A466  + (Forwards Revision 1 to Security Force Training & Qualification Plan.Plan Withheld (Ref 10CFR2.790))
  • ML19332A201  + (Forwards Revision 1 to Security Plan in Response to NRC .Revision Withheld (Ref 10CFR2.790))
  • ML20038A457  + (Forwards Revision 1 to Security Plan,Reflecting Requested Mods Per 770824 Meeting.Encl Withheld (Ref 10CFR2.790))
  • L-79-366, Forwards Revision 1 to Security Plan.Plan Withheld (Ref 10CFR2.790)  + (Forwards Revision 1 to Security Plan.Plan Withheld (Ref 10CFR2.790))
  • ML20041E390  + (Forwards Revision 1 to Security Plan.Revision Withheld (Ref 10CFR73.21))
  • L-81-186, Forwards Revision 1 to Security Training & Qualification Plan.Revision Withheld (Ref 10CFR2.790)  + (Forwards Revision 1 to Security Training & Qualification Plan.Revision Withheld (Ref 10CFR2.790))
  • ML20004A975  + (Forwards Revision 1 to Security Training & Qualification Plan.Revision 1 Withheld (Ref 10CFR2.790))
  • ML20050B169  + (Forwards Revision 1 to Security Training & Qualification Plan.Revision Withheld (Ref 10CFR73.21))
  • ML19338D105  + (Forwards Revision 1 to Snupps Fsar,Containing Responses to NRC Acceptance Review Questions & Addl Info Generated Since Initial FSAR Submittal in Oct 1979)
  • ML19249E801  + (Forwards Revision 1 to Special Order for Supplemental Info in Response to Ei Bulletins 79-06A & 79-06A,Revision 1. Recommendes Reactor Coolant Pressure to 400 Lbs Per Square Inch to Preclude Void Formation)
  • ML20005A989  + (Forwards Revision 1 to Spent Fuel Pool Mod for Increased Storage Capacity Re Licensing Rept on High Density Spent Fuel Racks)
  • ML20005A990  + (Forwards Revision 1 to Spent Fuel Pool Mod for Increased Storage Capacity Re Licensing Rept on High Density Spent Fuel Racks.)
  • ML18043A725  + (Forwards Revision 1 to Steam Generator Repair Rept)
  • ML18043A724  + (Forwards Revision 1 to Steam Generator Repair Rept)
  • ML19345C080  + (Forwards Revision 1 to Storage & in-transit Security Plan for SNM of Low Strategic Significance.Revision Withheld (Ref 10CFR2.790))
  • ML20003C812  + (Forwards Revision 1 to Suppl 2 of Seismic Re-evaluation. Rept Reflects Revisions to Analysis Re Emergency Diesel Generator & Cooling Water Heat Exchanger)
  • ML20003C813  + (Forwards Revision 1 to Suppl 2 of Seismic Re-evaluation. Rept Reflects Revisions to Analysis Re Emergency Diesel Generator & Cooling Water Heat Exchanger)
  • ML19319B147  + (Forwards Revision 1 to Supplemental Environ Rept & Info Re Accidents,Transportation & Transmission Lines.W/O Encl)
  • ML19319B146  + (Forwards Revision 1 to Supplemental Environ Rept & Info Re Accidents,Transportation & Transmission Lines.W/O Encl)
  • ML19317F238  + (Forwards Revision 1 to Supplemental Environ Rept & Info Re Accidents,Transportation & Transmission Lines.W/O Encl)
  • ML19317F242  + (Forwards Revision 1 to Supplemental Environ Rept & Info Re Accidents,Transportation & Transmission Lines.W/O Encl)
  • ML19340A198  + (Forwards Revision 1 to Supplemental Environ Rept,Consisting of Revised Pages to Suppl to Environ Quality Features of Keowee-Toxaway Project)
  • ML20031G387  + (Forwards Revision 1 to Svc Water Pump Structure Seismic Model, Revision 3 to Auxiliary Bldg Seismic Model & Technical Rept on Underpinning Auxiliary Bldg & Feedwater Isolation Valve Pits)
  • ML19340B147  + (Forwards Revision 1 to Sys Description of Submerged Demineralization Sys)
  • ML18043A442  + (Forwards Revision 1 to Table 3a of Semiannual Radioactive Effluent Release Rept for Jan-June 1978)
  • ML20125D265  + (Forwards Revision 1 to Task Action Plan A-33, NEPA Reviews of Accident Risks. Requests Approval of Scope of Pacific Northwest Lab Contract Terms & to More Accurately Reflect Thrust of Task)
  • ML20033B026  + (Forwards Revision 1 to Tech Spec Change Request 103 Requesting Amend to App a of License DPR-50,to Reflect NRC Review Comments)
  • ML20010A540  + (Forwards Revision 1 to Tech Specs, SAR Prepared to Support License Amend & Proposed Changes in Tech Specs, (Revision 1) & Environ Evaluation for Compliance w/10CFR51 Requirements, Supporting 810606 Application to Amend OL)
  • ML20028B213  + (Forwards Revision 1 to Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants, Providing Basis for Request to Perform Short Duration Integrated Leak Test (Type a))
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