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A list of all pages that have property "Title" with value "Safety Evaluation Supporting Util 890210 Final ATWS Design Description". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20151A017  + (Safety Evaluation Supporting Util 870209 Request for Relief from Requirements of ASME Section XI Re Hydrostatic Testing Requirements for Portions of Mods on Nuclear Svc Water Sys)
  • ML20214J094  + (Safety Evaluation Supporting Util 870211 Request for Relief from Inservice Inspection Requirement of 1974 Edition Through Summer 1975 Addenda of Section XI of ASME Code)
  • ML20209D756  + (Safety Evaluation Supporting Util 870211 Submittal Re Performance Enhancement Program,Finding 4-10)
  • ML20207S493  + (Safety Evaluation Supporting Util 870213 Request to Allow Temporary Transfer of Fuel Assemblies During Ultrasonic Fuel Insp in Spent Fuel Pool)
  • ML20216J756  + (Safety Evaluation Supporting Util 870302 QA Program)
  • ML18038A415  + (Safety Evaluation Supporting Util 870401 & 880606 Submittals on Compliance W/Atws Rule Re Alternate Rod Injection Sys & Recirculation Pump Trip Sys)
  • ML20155F353  + (Safety Evaluation Supporting Util 870414 Request for Authorization to Increase Power to 25% of Full Rated Power W/Listed Conditions.Licensee Evaluation of Operation & Proposal for Inspecting Components Must Be Augmented)
  • ML18032A707  + (Safety Evaluation Supporting Util 870526 Justification to Use Artificial Ground Motion Time History as Alternative Seismic Input for Seismic Sys Analyses)
  • NUREG-1137, Safety Evaluation Supporting Util 870601 Proposal Re Pipe Break Criteria Used for Flooding Analyses & Addition of Moderate Energy non-seismic Category I Piping to Exceptions List.Nrc Does Not Entirely Agree W/Util Justification  + (Safety Evaluation Supporting Util 870601 Proposal Re Pipe Break Criteria Used for Flooding Analyses & Addition of Moderate Energy non-seismic Category I Piping to Exceptions List.Nrc Does Not Entirely Agree W/Util Justification)
  • ML20236F765  + (Safety Evaluation Supporting Util 870626 & 0701 Surveillance Program & Results of Confirmatory Analyses Program.Util Satisfactorily Completed Confirmatory Analyses Program Demonstrating Adequacy of Basemat.Bnl Evaluation Rept Encl)
  • ML17055D724  + (Safety Evaluation Supporting Util 870708 Requests for Relief from Requirements of ASME Broiler & Pressure Vessel Code, Section XI Re Inservice Testing Program)
  • ML20235M161  + (Safety Evaluation Supporting Util 870708 Proposed Change to Tech Specs Concerning LPCI Subsystem Testing)
  • ML20236U182  + (Safety Evaluation Supporting Util 870724 Evaluation Demonstrating That Adequate Shoulder Gap Will Be Provided in Cycle 3 & Subsequent Cycles)
  • ML20148D439  + (Safety Evaluation Supporting Util 870731 & 1030 Submittals on Facility Compliance Re Alternate Rod Injection & Recirculation Pump Trip Sys,Per ATWS Rule 10CFR50.62)
  • ML20236F435  + (Safety Evaluation Supporting Util 870825 & 0923 Requests for Relief from Inservice Insp Requirements for Hydrostatic Testing of Svc Water Sys.Requests Granted)
  • ML20236D136  + (Safety Evaluation Supporting Util 870826 Request to Use Repair & Replacement Program Contained in ASME Section XI 1983 Edition Including Addenda Through Summer 1983)
  • ML18152B055  + (Safety Evaluation Supporting Util 871006 Request for Relief from ASME Section XI Hydrostatic Test Requirements Re Replacement of 4-inch Isolation Valve in Main Steam Sys)
  • ML20150D510  + (Safety Evaluation Supporting Util 871027 Submittal Re Reconfiguring Main Steam Line Rupture Detection Sys Bypass Indicating Lamp During Cycle 8 Refueling Outage)
  • ML20148H100  + (Safety Evaluation Supporting Util 871113 Proposed Tech Spec Changes Reflecting Unit 2 Cycle 2 Refueling & Addition of Boron Dilution Mitigation Sys for Unit 2)
  • ML20147E249  + (Safety Evaluation Supporting Util 871203 & 28 Requests to Use Core Bore Machine to Dismantle Lower Core Suport Assembly)
  • ML20055E304  + (Safety Evaluation Supporting Util 871223 & 880111 Proposed Changes to Tech Specs,Including Reducing Lower Limits of Detection for Liquid Radioactive Effluents)
  • ML20235Q034  + (Safety Evaluation Supporting Util 880324,0425,0610,0815 & 1006 Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes)
  • ML18033A373  + (Safety Evaluation Supporting Util 880429 Description of Reorganized Fire Brigade)
  • ML20062D700  + (Safety Evaluation Supporting Util 881123 & 900917 Responses to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Its Effect on Plant Operations. Submittals Acceptable.Beltline Welds Discussed)
  • ML18054B528  + (Safety Evaluation Supporting Util 881228 Analysis on Thermal Margin Audit Confirmatory Item Re Temp Qualification.Tech Specs Should Be Revised to Reflect Standing Order 54 Limits)
  • ML20245A616  + (Safety Evaluation Supporting Util 890210 Final ATWS Design Description)
  • ML20246M389  + (Safety Evaluation Supporting Util 890317 Proposed long-term Solution to Correct Rust Problems in Containment Spray Headers)
  • ML20247B489  + (Safety Evaluation Supporting Util 890330 Request to Eliminate Dynamic Effects of Postulated Primary Loop Pipe Ruptures from Design Basis of Plant,Using leak-before- Break Technology as Permitted by Revised GDC 4)
  • ML19332C723  + (Safety Evaluation Supporting Util 890413 Response to Item 2.2.1 of Generic Ltr 83-28, Equipment Classification Program for All Safety-Related Components)
  • ML20235M778  + (Safety Evaluation Supporting Util 890505 Relief Request 88-04 Re Addition of Insp Port on Containment Spray HX 1A)
  • ML17305A522  + (Safety Evaluation Supporting Util 890830 Request for Deviation from 10CFR50,Section III.G.2,App R Re Fire Protection)
  • ML20006F493  + (Safety Evaluation Supporting Util 890928 Request for Exemption to Allow Use of GMR-1 Canisters to Be Stored in Class C Storage Environ Vs Class a Storage Environ,Per ANSI N45.2.2)
  • ML17202G793  + (Safety Evaluation Supporting Util 900104 Proposal to Continue EPRI/ABB-ATOM Control Rod Demonstration Program Beyond Three Cycles of Operation & to Use B4C Control Rod W/ Minor Cracks During Cycle 12 Operation)
  • ML20006D543  + (Safety Evaluation Supporting Util 900115 Request for NRC Approval of Revised Capsule Withdrawal Schedule for B&W Master Integrated Surveillance Program)
  • ML17289A638  + (Safety Evaluation Supporting Util 900413 & 0928 Responses to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow)
  • ML20247A580  + (Safety Evaluation Supporting Util ATWS Mitigating Sys Actuation Circuitry Designs)
  • ML20244D529  + (Safety Evaluation Supporting Util Actions in Response to Generic Ltr 83-28,Position 4.5.2, Testing of Reactor Trip Sys. Justification for Not Testing Reactor Mode Switch or Backup Scram Valves Provided)
  • ML19340E623  + (Safety Evaluation Supporting Util Actions in Response to IE Bulletin 79-13, Cracking in Feedwater Sys Piping)
  • ML17255A252  + (Safety Evaluation Supporting Util Actions to Resolve Problems During Tube Pull & Steps Taken to Maintain Steam Generator Integrity)
  • ML20247C017  + (Safety Evaluation Supporting Util Actions to Recover from 890307-08 Unit 1 Steam Generator Tube Rupture Event)
  • ML17156A890  + (Safety Evaluation Supporting Util Actions Re Compliance W/ 10CFR50.62, ATWS, Specifically Alternate Rod Injection, Standby Liquid Control Sys & Recirculating Pump Trip Sys)
  • ML17223A275  + (Safety Evaluation Supporting Util Actions to Comply W/ Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability On-Line Functional Testing of Reactor Trip Sys. Item Complete)
  • ML20235J342  + (Safety Evaluation Supporting Util Action in Response to Generic Ltr 83-28,item 2.1 (Part 2) Confirming Establishment of Interface W/Either NSSS Vendor or Vendors of Each Component in Reactor Trip Sys)
  • ML20010E622  + (Safety Evaluation Supporting Util Action Taken to Modify Controls for Steam Dump Valves)
  • ML13330B193  + (Safety Evaluation Supporting Util Addl Info Re post-fire Alternative Shutdown Sys Design)
  • ML20062E302  + (Safety Evaluation Supporting Util Analysis of Main Steam Line Break W/Continued Feedwater Addition)
  • ML18087A556  + (Safety Evaluation Supporting Util Analysis of Main Steam Line Break W/Continued Feedwater Addition (IE Bulletin 80-04))
  • ML19219B290  + (Safety Evaluation Supporting Util Analysis Re Susceptibility of safety-related Sys to Flooding from Failure of non- Category 1 Sys)
  • ML20062E282  + (Safety Evaluation Supporting Util Analysis Submitted Per IE Bulletin 80-04 of Main Steam Line Break W/Continued Feedwater Addition,Submitted Per IE Bulletin 80-04)
  • ML19323B098  + (Safety Evaluation Supporting Util Analysis of Postulated Fuel Handling Accident Inside Containment)
  • ML20214X111  + (Safety Evaluation Supporting Util Analytical Methods Used to Evaluate Stresses of Critical Components for Vacuum Breaker Integrity Re Mark I Containment Program)
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