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A list of all pages that have property "Title" with value "Forwards Response to NRC Request for Addl Info on AP600 Topics". 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

  • ML20059C322  + (Forwards Response to NRC Request for Addl Info on Sbwr Design)
  • ML20116P035  + (Forwards Response to NRC Request for Clarification Re Concurrent Use of ASME Code Cases N-416 & N-498 Re post-mod Hydrostatic Test & 10-yr Sys Hydrostatic Pressure Test of Main Steam Sys,Respectively)
  • ML18152B437  + (Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections)
  • ML20248G527  + (Forwards Response to NRC Request for Clarification of 890803 Application for Amends to Licenses DPR-29 & DPR-30 Re HPCI & Rcic.Revised Temp Setpoint Is 170 F,Based on Impell Corp Calculation)
  • ML20211L915  + (Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity)
  • PY-CEI-NRR-1838, Forwards Response to NRC Request for Comments on Precursor Analysis of Emergency Core Cooling System & Svc Water Pipe Break Incidents  + (Forwards Response to NRC Request for Comments on Precursor Analysis of Emergency Core Cooling System & Svc Water Pipe Break Incidents)
  • ML19312D908  + (Forwards Response to NRC Request for Data to Evaluate Code Predictions for Steam Separation & Two Phase Natural Circulation Conditions Applicable to TMI Accident)
  • ML20238F568  + (Forwards Response to NRC Request for Description of Operation W/Partially Filled Rcs,Per Generic Ltr 87-12.Util Working w/C-E Owners Group to Review Loss of RHR Leading to RCS Pressurization & Potential Coolant Ejection)
  • A02823, Forwards Response to NRC Request for Documentation of Four Open Items Re SEP Topic III-6, Seismic Design Considerations. Final Responses on Structural Analysis Currently Scheduled for Submittal on or About 830207  + (Forwards Response to NRC Request for Documentation of Four Open Items Re SEP Topic III-6, Seismic Design Considerations. Final Responses on Structural Analysis Currently Scheduled for Submittal on or About 830207)
  • ML20042D114  + (Forwards Response to NRC Request for Feedwater Check Valve V28B Flaws Evaluation.Evaluation Addresses Two Flaws Detected During Cycle 13 Outage Inservice Insp of Valve.Util Will Repair or Replace Valve)
  • ML20069B718  + (Forwards Response to NRC Request for Further Clarification on Soil Amplification Issue, Per NRC .Info Adequate to Close SER Outstanding Issue 3 in Next SER Suppl)
  • ML19260C523  + (Forwards Response to NRC Request for Info Re Implementation of NUREG-0578 Recommendations.Two Oversize Drawings Encl)
  • ML20080A296  + (Forwards Response to NRC Request for Info Re Valve Maint Performed During 831007 & 1101 Outage,Consisting of List of Exposures)
  • GO2-81-511, Forwards Response to NRC Request for Info Re Fire Protection Evaluation Rept  + (Forwards Response to NRC Request for Info Re Fire Protection Evaluation Rept)
  • ML20205Q905  + (Forwards Response to NRC Request for Info Re Status of Reg Guide 1.97 Implementation.Util Intends to Provide Category 3 Containment Temp Indication as Originally Committed in)
  • ML18066A873  + (Forwards Response to NRC Request for Info Per 10CFR50.54(f) Re Adequacy & Availability of Design Basis Info)
  • ML20134L426  + (Forwards Response to NRC Request for Info Per 10CFR50.54(f) Re Adequacy & Availability of Design Basis Info)
  • ML20134H221  + (Forwards Response to NRC Request for Info Re Adequacy & Availability of Design Info,Per 10CFR50.54(f). Bases Info)
  • ML19305B295  + (Forwards Response to NRC Request for Info Re Welding Process & Heat Treatment in Cladding Vessel Nozzles.Base Matl of All Nozzles Is ASTM A-508,Class 2.Preheat Temp Is 250 F Min & post-heat Temp Is 400 F)
  • ML20207C819  + (Forwards Response to NRC Request for Info Re Nuclear Svc Cooling Water (NSCW) Sys Performance Made at 861215 Meeting. Encl Includes NSCW Water Hammer Evaluation)
  • ML19323H716  + (Forwards Response to NRC Request for Info Re Facility Mar 1980 Eddy Current Insp.Info Provided Re Number of Eddy Current Indications Recorded in Steam Generator a & B Hot Legs & Distribution by Size & Height Above Tubesheet)
  • ML20246C977  + (Forwards Response to NRC Request for Info Re Condition of Drywell Paint,Per Insp Rept 50-271/89-80)
  • ML19253C895  + (Forwards Response to NRC Request for Info Re Loss of Offsite Power.Outline of Pertinent Events Encl)
  • ML20127A026  + (Forwards Response to NRC Request for Info Re Category C-2 Steam Generator Tube Insps Per NUREG-0844,completing Response to Generic Ltr 85-02)
  • BSEP-94-0355, Forwards Response to NRC Request for Info During Telcons W/ Util Re 930125 CRD Scram Accumulator Lar.Ref Noted in 930125 Basis for Amend Request (NEDE-14584, Assurance of Acceptable Scram Through CRD Speed Analysis) Also Encl  + (Forwards Response to NRC Request for Info During Telcons W/ Util Re 930125 CRD Scram Accumulator Lar.Ref Noted in 930125 Basis for Amend Request (NEDE-14584, Assurance of Acceptable Scram Through CRD Speed Analysis) Also Encl)
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